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DESCRIPTION OF ACTION FOR THE IMPLEMENTATION OF THE FUSION ROADMAP IN 2021-2027 Annex 1 - Part B Chapter 3
Please note that this is a draft version of Chapter 3 of the Grant proposal. It is a further evolved version of the one that has been distributed by the end of 2019 to GA, STAC and EFPW. But it is still being worked at by PMU and the writers group. The present version is mainly attached to the call to give a fair idea what topics are covered by each of the work packages.
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Change Log Reason for change Version Date Original version given to the PMU team 1 23/02/2020 New version after the various subsections have been reworked by PMU 2 03/04/2020
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Participant No. Participant Short name Country 1 (Coordinator) MPG Germany 2 OEAW Austria 3 LPP-ERM-KMS Belgium 4 INRNE Bulgaria 5 RBI Croatia 6 UCY Cyprus 7 IPP.CR Czech Republic 8 DTU Denmark 9 UT Estonia 10 VTT Finland 11 CEA France 12 FZJ Germany 13 KIT Germany 14 NCSRD Greece 15 WIGNER RCP Hungary 16 DCU Ireland 17 ENEA Italy 18 ISSP-UL Latvia 19 LEI Lithuania 20 NWO-I-DIFFER Netherlands 21 IPPLM Poland 22 IST Portugal 23 IAP Romania 24 CU Slovakia 25 JSI Slovenia 26 CIEMAT Spain 27 VR Sweden 28 EPFL Switzerland 29 CCFE United Kingdom 30 KIPT Ukraine
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Table of Contents
Change Log ...... 3 3. IMPLEMENTATION ...... 7 3.1 Overall Implementation of the Programme ...... 7 Campaign oriented implementation ...... 7 Project orientated implementation ...... 8 Table 3.1a List of Work Packages ...... 8 Table 3.1b List of Deliverables ...... 9 Table 3.1c List of Milestones ...... 9 Table 3.1d List of Critical Risks & Mitigation Strategy ...... 9 3.2 Fusion Science ...... 10 01 EU Tokamaks Exploitation and Theory-Simulation-Verification-Validation (WPTE) ...... 10 02 Exploitation of JT-60SA and Theory-Simulation-Verification-Validation (WPSA) ...... 20 03 Exploitation of W7-X and Theory-Simulation-Verification-Validation (WPW7X) ...... 22 04 Advanced Computing (WPAC) ...... 27 05 Plasma Wall Interaction and Exhaust and Theory-Simulation-Verification-Validation (WPPWIE) ...... 30 06 Preparation of ITER Operation (WPPrIO) ...... 37 07 Enabling Research (WPENR) ...... 41 3.3 Fusion Technology ...... 43 08 Design-assist Activities (WPDES, directed by the DCT) ...... 44 09 Magnet System (WPMAG) ...... 53 10 Breeding Blanket (WPBB) ...... 57 11 Plant Electrical Systems (WPPES) ...... 64 12 Divertor (WPDIV) ...... 68 13 Heating & Current Drive (WPHCD) ...... 77 14 Tritium, Fuelling & Vacuum (WPTFV) ...... 82 15 Balance of Plant (WPBOP) ...... 87 16 Diagnostics & Control (WPDC) ...... 91 17 Remote Maintenance (WPRM) ...... 94 18 Materials (WPMAT, incl. MAT-TBM collaboration) ...... 102 19 Safety & Environment (WPSAE) ...... 107 20 Early Neutron Source (WPENS) ...... 110 21 Prospective R&D (WPPRD) ...... 115 22 Socio Economic Studies (WPSES) ...... 121 3.4 Communications ...... 123 23 Communications (WPCOMM) ...... 123 3.5 Training and education ...... 127 24 Training and Education (WPTRED) ...... 127 3.6 Management ...... 131 25 Programme Management Unit (WPPMU) ...... 131 3.7 Technology Transfer ...... 133 26 Technology Transfer (WPTT) ...... 133 3.8 International Collaborations Coordination (INCO) ...... 135 Page 5 of 143
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Programmatic context impacting the approach to international collaboration ...... 136 High-level guidelines for international collaboration ...... 137 Implementation of international collaborations ...... 137 Main topics identified for collaboration with the international partners ...... 138 3.9 Industrial Involvement ...... 301
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3. IMPLEMENTATION 3.1 Overall Implementation of the Programme The implementation of the activities is broken down into Work Packages (WP) that mirror the structure of the programmatic deliverables. An overview of all WPs in alphabetic order, and their relation to the roadmap missions is given in Fig. 3.1. Acronym Work Package Mission 1 Mission 2 Mission 3 Mission 4 Mission 5 Mission 6 Mission 7 Mission 8 AC Advanced Computing BB Breeding Blankets BoP Balance of Plant COMM Communications DC Diagnostics & Control DES Design Activities DIV Divertor Engineering ENS Early Neutron Source ENR Enabling Research HCD Heating & Current Drive MAG Magnets MAT Materials PES Plant Electrical Systems PRD Prospective Research & Development PrIO Preparation of ITER Operation PWIE Plasma Wall Interaction & Exhaust RM Remote Maintenance SA JT60-SA Exploitation & TSVV SAE Safety and Environment SES Socio-Economic Studies TE Tokamak Exploitation & TSVV TRED Training and Education TFV Tritium Fuelling & Vacuum TT Technology Transfer W7X W7-X Exploitation & TSVV Figure 3.1: Overview of all Work Packages and their relation to the roadmap missions
This Chapter outlines the WPs in which the Work Plan will be implemented. For each WP, the top- level management scheme is given along with a description of the deliverables. The dates in brackets for the key deliverables are indicative. The detailed breakdown will be elaborated through Project Execution Plans. For all WPs competitive Calls for Participation among the Consortium members will be organised. The contribution of members will be selected by the Project Leaders/Task Force Leaders on the basis of documented expertise in each area. This way of implementing the programme promotes excellence in each WP. Figure 3.2 gives an overview on how the various Work Packages are arranged in the Departments.
Campaign oriented implementation Work on tokamak and stellarator devices will be conducted via a campaign oriented approach, with a coordination structure based on Task Forces, which are groups established to execute tasks linked by common scientific and technical objectives. A collegium of Task Force Leaders will be responsible for organising the exploitation of all tokamak and stellarator devices planning and optimising the experiments on the different devices following the priorities of the Fusion Roadmap. The Terms of Reference for the Task Force Leaders and their Deputies are given in Chapter 4. Each annual work plan indicates the Missions to be addressed and the corresponding estimate of the fraction of device time to be allocated. In case of facility unavailability that prevents the programme to be exploited in part or in full, the timeline of the experiment will be amended by the Task Force Leaders in consultancy
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Version 6 May 2020 with the Programme Manager and facility operator. The Consortium will refund the share of the cost agreed beforehand..
EUROfusion Programme Management
International Communicatio Collaborations n
Training and COMM Education TRED
Fusion Fusion Science Administration Technology Tokamak & Plasma Early Advanced Enabling Prospective Stellarator Facing DEMO Design Neutron Computing Research R&D Exploitation Components Source TE AC PWIE ENR BB ENS PRD TT SA BoP SES PMU W7X DC PrIO DES DIV HCD MAG MAT PES RM SAE TFV Figure 3.2: Overview of all Work Packages and their organisation within the various departments
Project orientated implementation Design work, realisation of components and specific scientific and technical work on facilities will be implemented in the form of Projects. This form will also be applied to R&D tasks that are more specific than those that are conducted via campaigns. For each Project, a Project Leader is appointed. The Terms of Reference for the Project Leader are listed in Chapter 4. Within the DEMO Design Project, the WPs are organised using such project approach. The WPs are distributed across geographically distributed teams, with defined scopes, deliverables, time schedules and resource allocation, and managed by a centralised programme unit as detailed further in Chapter 4. Table 3.1a List of Work Packages The list of the Mission related Work Packages is given below with a description of each in the following subsections:
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Work Work Missions Lead Lead Person- Start Finish package package impacted participant participant months month month No Title No short name 1 Tokamak Exploitation (WPTE) 1,2,4 1/1/2021 31/12/2025 2 JT-60SA Exploitation (WPSA) 1,2 1/1/2021 31/12/2025 3 W7-X Exploitation (WPW7X) 1,2 1/1/2021 31/12/2025 4 Advanced Computing (WPAC) 1-8 1/1/2021 31/12/2025
5 Plasma Wall Interaction and 2,3,6,8 1/1/2021 31/12/2025 Exhaust (WPPWIE) 6 Preparation of ITER Operation 2,6 1/1/2021 31/12/2025 (WPPrIO) 7 Enabling Research (WPENR) 1-8 1/1/2021 31/12/2025 8 Design Activities (WPDES) 1-6 1/1/2021 31/12/2025 9 Magnet system (WPMAG) 6 1/1/2021 31/12/2025 10 Breeding Blanket (WPBB) 3,4,6 1/1/2021 31/12/2025 11 Plant Electrical Systems (WPPES) 6 1/1/2021 31/12/2025 12 Divertor (WPDIV) 2,6 1/1/2021 31/12/2025 13 Heating and Current Drive 6 1/1/2021 31/12/2025 systems (WPHCD) 14 Tritium, fuelling & vacuum 6 1/1/2021 31/12/2025 systems (WPTFV) 15 Heat transfer, balance-of-plant 6 1/1/2021 31/12/2025 and site (WPBOP) 16 Diagnostic and control (WPDC) 1,6 1/1/2021 31/12/2025 17 Remote Maintenance Systems 6 1/1/2021 31/12/2025 (WPRM) 18 Materials (WPMAT) 3,6 1/1/2021 31/12/2025 19 Safety and Environment 5,6 1/1/2021 31/12/2025 (WPSAE) 20 Early Neutron Source (WPENS) 3 1/1/2021 31/12/2025 21 Prospective Research & 1,2,8 1/1/2021 31/12/2025 Development (WPPRD) 22 Socio-Economic Studies (WPSES) 1-8 23 Communication (WPCOMM) 1-8 1/1/2021 31/12/2025 24 Training and Education 1-8 1/1/2021 31/12/2025 (WPTRED) 25 Programme Management Unit 1/1/2021 31/12/2025 (WPPMU) 26 Technology Transfer (WPTT) 1-8 1/1/2021 31/12/2025 Table 3.1b List of Deliverables Del. Deliverable WP Short name of lead Type Dissemination Delivery (no.) name No. participant level date Table 3.1c List of Milestones Table 3.1d List of Critical Risks & Mitigation Strategy
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3.2 Fusion Science 01 EU Tokamaks Exploitation and Theory-Simulation-Verification-Validation (WPTE) Objectives The main objective of the WP on the exploitation of the EU tokamaks (WPTE) is to provide the physics basis for ITER and DEMO integrated scenarios in a stepladder approach with machines of different capabilities, sizes and parameters. As no single facility has the possibility to completely test ITER or DEMO scenarios, each EUROfusion facility will address different aspects of the operating scenarios in a coordinated manner and in a specific operational range. The integration of the developed knowledge for ITER and DEMO is ensured via theory and simulation. The WP addresses mainly the Mission 1 and Mission 2 issues of the Fusion Roadmap, though synergies will be developed with Mission 8, e.g. on long-pulse operation and 3D plasma physics aspects. The WPTE coordinates the scientific programmes performed on JET, ASDEX Upgrade, TCV, MAST Upgrade, WEST and COMPASS-U1. These EU facilities have unique and complementary capabilities that allow addressing crucial ITER and DEMO physics issues, including 3D perturbation coils (AUG, MAST-U), high shaping flexibility (TCV), a full W wall (AUG, WEST), an ITER like Wall with tritium capability (JET), alternative divertor configurations (AUG, TCV, MAST-U and possibly COMPASS-U) and ITER/DEMO like heating systems (AUG, MAST-U, TCV, WEST, COMPASS-U). JET has unique capabilities for supporting ITER, as it is the only tokamak capable of operation with tritium and the only one that has the ITER first wall materials. A set of high priority programmatic deliverables2 have been elaborated in agreement with the ITER International Organisation, for which further JET operation up to 2024 can make unique and essential contributions to the ITER research plan. The main objectives of this extension are to test and improve key ITER systems and technology3, and, to validate and optimize key elements of ITER operation4. For this, another DT-experimental campaign (DTE3) is foreseen by 2023, while the preparation of the final decommissioning will take place in 2024. In addition, it has been recognized that DEMO and future fusion power plants will require plasma scenarios that may significantly differ from those that are anticipated for ITER, and need to be further developed. Experimental efforts on the Medium Size Tokamaks (MST) will be focused on aspects beyond ITER (no ELMs, disruption free, radiative scenarios, high beta). These may also ultimately benefit to the ITER operation beyond Q=10. Extensive enhancements are implemented to a number of EUROfusion common facilities (ASDEX Upgrade, MAST Upgrade, TCV and WEST) to support the plasma exhaust strategy for DEMO. The completion of the plasma exhaust enhancements and their full exploitation are crucial for achieving the goals of the fusion roadmap Mission 2. The outcome of this research will indicate which prototype divertor configuration should be installed on the DTT device, which will then test its applicability for
1 Following a positive conclusion of a facility review that should take place by 2023 which is close to the time when COMPASS-U should enter into operation. 2 The “Case for the exploitation of JET beyond 2020 in support of ITER” (EUROFUSION GA (18) 23 - 4.6d) has been positively reviewed by the EUROfusion STAC (EUROFUSION GA (19) 25 - 4.4c). In addition, the General Assembly was presented with a copy of a letter of support for the JET programme beyond 2020 from the ITER Director General (EUROFUSION GA (19) 25 - 4.4c). 3 ITER’s disruption mitigation system, ITER’s tritium monitoring and removal systems and techniques, diagnostic mirrors and key diagnostics for ITER, key remote handling processes for ITER. 4 Nitrogen seeded operation in view of ITER seeding gas selection, test and optimise key elements of ITER’s strategy for operation with the Be/W wall, preparation of ITER integrated operation with low disruptivity, preparation of ITER Pre-fusion Power Operation, test and optimise key elements of ITER Fusion Power Operation. Page 10 of 143
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DEMO. According to the planning, such input should be defined in 2023, when also COMPASS-U should come in operation. Around this time, EUROfusion will organize a facilities review to assess which devices should be part of the EUROfusion programme from the year 2026 onwards. Key Enhancements to support the scientific programme The completion of the PEX projects for enhancements by the end of 2023 is crucial for achieving the goals of the Fusion Roadmap. The current timeline (as per end of 2019) is shown in figure 3.3.
Figure 3.3: Timeline for the PEX projects (as for Oct 2019). FZJ is the JULE-PSI project that is part of the WP PWIE 1. ASDEX Upgrade will be equipped with a modified upper divertor: Change of the upper divertor target structure; Installation of a new pair of in-vessel PF coils in the upper divertor; Installation of a cryo-pump in the upper divertor, providing pumping through the private flux region; Diagnostic enhancements for the upper divertor. 2. The MAST-Upgrade project upgrades the spherical tokamak to enable the exploration of a wide variety of divertor configurations including the Super-X. The proposal is separated into two phases: Phase I (by 2021): A cryo-plant for the installed divertor cryo-pump and NBI upgrade; Diagnostics, a pellet injector, additional gas valves, and control enhancements. Phase II (by 2023);
An NBI Double Beam Box which would increase the Ptot/R-value from 5.9 MW/m to 11.8 MW/m. 3. The TCV project is an upgrade to the TCV tokamak (to be completed by 2021) and aims to enable high density operation with auxiliary heating. The project is linked to a power upgrade funded by the Swiss government. It will raise the maximum available auxiliary power coupled to the plasma to 6.75
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MW, including 2 MW of NBI. The power upgrade will result in Ptot/R of 7.7 MW/m. The TCV project includes: A gas baffle to increase divertor neutral compression from 5-10 to an estimated 200; Cryopumps for improved density control; Additional gas valves and SOL/divertor diagnostics for detachment control; Completion of all divertor diagnostics 5. The WEST project involves implementing a full-actively cooled divertor with ITER-like plasma facing units (2021). These would enable the WEST tokamak to make full benefit from its long pulse capability, particularly in support of ITER tungsten divertor operation. The WEST PEX project includes: the procurement of the divertor plasma facing units and their qualification on dedicated testbeds, their assembly on thirty degrees sector supports and their integration in the divertor inside the WEST vacuum vessel; enhancement in instrumentation for their monitoring during plasma operations; a new edge Thomson scattering diagnostic to provide simultaneously the upstream temperature and density profiles. In addition, enhancement projects are foreseen on JET on the basis of ITER diagnostic development requests and to enhance capabilities for ITER relevant scientific exploitation. Priorities have been discussed and agreed between EUROfusion and the relevant stakeholders including ITER-IO. The JET upgrades include: A second shattered pellet injector (SPI) system, with a similar design to the existing one, to be installed in place of an existing disruption mitigation valve system. The two systems will then be operated together. Two additional diagnostic systems, wide angle bolometry and a fast camera, required to view and measure the effects of the second SPI, will be developed. ITER relevant Laser Induced Desorption system (LID-QMS) and Laser Induced Breakdown Spectroscopy (LIBS): LID-QMS is developed for ITER-like tritium surface inventory measurement. JET will exactly replicate the LID-QMS technology for ITER to be used for inventory monitoring. In addition, an ITER-like Laser Induced Breakdown Spectroscopy system, LIBS, for training and testing purposes will be deployed using the remote handling arm during maintenance. Diagnostics essential to exploit edge physics, divertor and plasma wall interaction deliverables for ITER.
Further possible upgrades may be undertaken in the context of ITER mirror testing, imaging, spectroscopy, neutrons, alpha particles, Langmuir probes, pressure gauges, reflectometry.
The foreseen key enhancements are summarised below (listed are the years in which the upgrades will become operational)
Year JET AUG MAST-U TCV WEST 2021 Shattered pellet Cryo-pumped 1 MW 2nd NBI Lower divertor injection (SPI)1) upper and lower (cntr.-inj.) upgrade (PEX) Divertor TS (RT divertor. 1.4 MW X2 Boron limiters capable) High frequency (lateral) Impurity Imaging heavy ion pellet injector. 0.9 MW X3 powder beam probe High fidelity gas (lateral) dropper (IPD) fuelling system. 1.9 MW dual High resolution X2/X3 (lateral or edge TS system top launch)
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Full PEX upgrade (2 sets of baffles + diagnostics) 2022 Second Cryo-pumped Divertor cryo- 3×1MW ECRH Shattered upper and lower pumping1) long pulse pellet divertor injection X-point Thomson (SPI) Scattering. wide angle Longer flux swing bolometry (higher Ip or and fast longer flat-top) camera LIDS 2023 LIBS ITER Upper divertor Double beam box LIBS system mirror upgrade (PEX) (2.5 MW off axis + embarked on 2.5 MW tilted) the AIA 2024 Neutron damaged 2 MW EBW Alternative materials for heating4) material injection divertor for RE control2) manipulator3)
1)Depending on feasibility study. 2)Depending on technology availability and feasibility study. 3)Depending on availability of irradiated materials (funding). 4)Depending on national funding of STEP project. Description of work Key focus points of the programme are summarised in the table below
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Year Miss JET AUG MAST-U TCV WEST ion 21 M1 Helium H-mode SPI studies ELM control Disruption high access and its Disruption (RMP, pellet) handling/advanc confinement extrapolation to handing/advance DEMO ed control scenario D and DT plasma d control scenarios DEMO scenarios with ECRH DEMO scenarios validation validation (no- /boron validation (no- (no-ELM) ELM, negative limiters ELM) triangularity) M2 Characterise PWI Erosion studies Access to Access to and High fluence in Helium for the Detachment detachment control of D campaign ITER Pre-Fusion control Alternative detachment, Real time Power Operation divertor baffling conditioning phase concepts 22 M1 Install and test SPI studies ELM control Isotope studies Long pulse H 2nd shattered Disruption (RMP, pellet) Disruption mode: W pellet injectors handling and DEMO handling/advanc control Low disruptivity control scenarios ed control scenario Isotope studies validation DEMO scenarios (no-ELM, validation negative triangularity) M2 Characterise Isotopes studies Alternative Alternative High fluence plasma-wall on detachment divertor divertor D/He interaction in concepts concepts at campaign seeded scenarios Detachment higher power Control of N and Ne- control loads, heat load detached seeded in DD studies operation in long pulse 23 M1 Scenario Integrated DEMO DEMO scenarios Fully non- integration in DT plasma control scenarios validation (no- inductive H- for ITER (seeded, IBL scenarios validation ELM, negative mode low disruptivity) (no-ELM, triangularity) operation negative Low torque IBL triangularity) Integrated Fast-ion plasma control physics M2 N and Ne-seeded Alternative upper Alternative Isotope studies High fluence in DT in view of divertor divertor on detachment D and seed ITER seeding gas configurations concepts at impurity selection. high power campaign N and Ne density Control of retention in PFC Isotope detached ITER tritium studies on operation in housekeeping detachment DN and fuel recovery
24 M1 High βN scenarios Fast ion High βN Disruption DEMO scenarios physics. scenarios free long validation High βN Low torque IBL pulse (negative scenarios Fast ion physics campaign triangularity) IBL scenarios
M2 laser induced Alternative upper Alternative Neutral physics Actively breakdown divertor divertor in Alternative cooled W spectroscopy configurations concepts at divertor PFC in-situ tritium Heat load studies high power concepts protection surface inventory in alt. div. config. density. (pumping & scheme characterisation Detachment baffling) Test DEMO and removal control at PFU techniques high power densities Page 14 of 143
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Assess ammonia production and clean-up 25 M1 DEMO scenarios Disruption Alternative High density validation (no- handling. methods for RE / radiation ELM, negative Fast-ion handling. regimes triangularity) physics. Disruption (pellet) in Disruption DEMO handling long pulse handling scenarios prototype prototype validation (no-ELM, negative triangularity M2 Neutron Detachment Neutral physics Assessment damaged control at in Alternative of ITER grade materials high power divertor PFU lifetime PEX Modelling densities concepts Test DEMO validation PEX (pumping & PFU Modelling baffling) validation PEX Modelling validation
Mission 1 – Plasma Regimes of Operation JET campaigns until the end of 2020 have to focus on hydrogen isotope studies and scenarios for high and stationary DT fusion power. From 2021 up to 2024, the campaign time will be used for: 1. Preparing the low activation phase of ITER using helium (H-mode) operation with a Be/W wall; 2. Validating disruption management for ITER, in particular mitigation with multiple SPI systems and strategies for disruption detection & avoidance; 3. Developing power and particle exhaust solutions in high performance scenarios with a radiative divertor (Ne & N2) and a metallic wall; 4. Verifying the ITER Research Plan towards Q=10 including DT integrated operation (DTE3) at full performance with low disruptivity including Nitrogen seeding. The exploration of the baseline ELMy H-mode operating space that will be conducted on EU tokamaks will serve as a basis for the development of the safe operational scenario on ITER and the optimisation of fusion performance. In coordination with WPPrIO, a comprehensive assessment of the operational strategy for ITER will be provided, supported by state-of-the-art integrated modelling tools (also validating the IMAS framework) by 2024. The flexible heating mix and wide parameter space will be used to assess the impact of ion and electron heat channels as well as plasma rotation on the plasma and pedestal performance by 2023. Further development of suitable RF heating schemes and isotope transport studies will be performed in support of hte ITER non-nuclear phase (H and He plasmas). Beyond this, the experimental programme will allow access to a wide parameter space including high βN non-inductive scenarios and it will guide needed theory development. High βN plasmas will be used for the validation of physics effects reducing anomalous transport in these scenarios. This will provide input for JT60-SA and the steady-state advanced scenarios for ITER and DEMO by 2024. The role of fast ions will be clarified by using the fast-ion modelling workflow simulating self-consistently the stabilising effect of fast ions on thermal transport, their impact on MHD stability, evolution of Alfvén modes and main plasma parameters in presence of fast ions. The validation of such workflow is needed for more reliable estimation of the ITER DT performance and development of strategies and techniques for fast ion control. State-observer based control systems as foreseen on ITER and DEMO have been implemented on AUG and TCV, and will be implemented on MAST-U. This activity allows direct development of ITER prototype control schemes and will guide the DEMO control design. Within this framework, a proof of Page 15 of 143
Version 6 May 2020 principle for a full disruption handling system will be obtained. This will include safe scenario control with disruption prevention for all known disruption paths, disruption mitigation and runaway electron (RE) beam handling. RE mitigation with SPI (likely available on AUG from 2021) and other material injection techniques as well as alternative RE handling methods (3D fields, ECRH, ICRH) will be tested. Tolerable edge conditions with small or no ELMs are important for ITER and crucial for DEMO. Codes providing predictive capability for active ELM control using 3D perturbation fields including the simulation of divertor heat loads, fast-ion confinement and global plasma stability will be validated and used to assess the impact on ITER, possibly by 2024. This includes integrated core-pedestal-SOL modelling to understand and predict the impact of the high separatrix density and impurity content needed to reach partial or full detachment in the ITER/DEMO divertors on pedestal performance and edge stability. Small and no-ELM scenarios will be assessed on MST facilities, in view of their applicability to ITER and DEMO, before they are ported to the larger devices (JET, JT-60SA). Cross- machine comparisons will help identifying the operational space of QH-modes, I-modes and other ELM-free scenarios, which are already established on single EU devices or can be ported from non-EU devices. These scenarios will be tested with respect to the requirements for future devices (e.g. compatibility with pellet fuelling and detachment, transition to and from the high confinement mode) by 2024.
Mission 2 – Heat Exhaust Systems The core of the work on plasma exhaust, in close coordination with WPPWIE, consists of the exploitation of the Plasma EXhaust (PEX) upgrades to the divertors of AUG, TCV, MAST-U and WEST. On JET, the Mission 2 activity will grow in importance, focusing in developing power and particle exhaust solutions with the ITER like wall in high performance D and D-T scenarios with a (semi) detached radiative divertor (Ne & N2). All these investigations will provide the physics basis and validated modelling tools for ITER divertor operation and the decision on the divertor configuration for DTT by 2023, while informing the DEMO design case of the potential benefits of the alternative divertor configurations. As divertor physics is not easily scalable to larger devices, extensive model validation and verification are needed for credible extrapolations. This modelling will guide the programme throughout FP9, testing and validating an increasing number of sophisticated tools over time. The large flexibility of accessible divertor configurations with different wall materials will be used to challenge existing Scrape-Off-Layer (SOL) codes and aid the development of reduced SOL transport models. A comparison between conventional and advanced divertor configurations will be conducted, in terms of access to and control of detachment. Configuration and detachment control during transient events (ELMs, sawteeth, pellets, etc.) as well as the entry and exit from and to L-mode will be demonstrated using ITER/DEMO relevant sensors and actuators. The compatibility of alternative configurations with active ELM-control techniques (3D fields, pellets) and ELM-free scenarios will be tested by 2024. The potential of these configurations for ELM energy buffering in high radiation, fully or partially detached scenarios, will provide crucial information on the requirements for the ITER/DEMO edge. The activities on plasma facing components will be conducted in close coordination with WPPWIE and will focus on the impact of seeding gases and transients on the erosion and lifetime of the components, for conventional and innovative configurations, including effects due to the presence of 3D fields. Urgent ITER R&D questions will be addressed at the beginning of FP9. In addition, novel plasma-facing materials, e.g., foreseen for the 2nd ITER divertor and for DEMO will be tested and their role in component lifetime and plasma compatibility will be assessed in order to prepare a reliable operation of future devices by 2024. Theory and Simulation developments In FP9, activities in theory and simulations of plasma and fusion systems will be significantly intensified. These activities constitute an integral part of the WPTE, in support of interpreting and Page 16 of 143
Version 6 May 2020 preparing tokamaks experiments, and for predicting ITER and DEMO operational scenarios. The development of theory and computational tools will be coordinated by the E-TASC scientific board. Specific Theory, Simulation, Validation and Verification (TSVV) tasks will be embedded in the relevant WPs, to: 1) Validate the predictive capability of L-H transition and pedestal physics for ITER and DEMO, addressing in particular: a. H-mode access and characteristics, and confinement optimization close to the L-H transition; b. SOL pedestal modelling, with self-consistent modelling of instabilities during pedestal evolution and self-consistent calculation of pedestal width; c. The features of small/no ELM regimes, in view of their transferability to ITER and DEMO; d. Edge properties of negative triangularity and, more generally, strongly shaped configurations. 2) Model MHD transients in an integrated fashion, to support the European experimental programme on disruptions and ELMs, addressing in particular: a. Full MHD and realistic wall representation, including wall currents; b. The optimisation of the transient/unstable plasma current ramp-up and ramp-down phases for ITER and DEMO scenarios; c. Real-time disruption detection and avoidance tools, improving and using reduced models such as in RAPTOR, for disruption management ; d. Runaway electron dynamics . 3) Validate the predictive capability of burning plasma physics phenomena for ITER and DEMO, addressing in particular: a. Interaction of turbulence, MHD modes, and energetic particles; b. Improved fast particle calculations (for ICRH, and for alpha-particle physics) in integrated pedestal-core transport and stability predictions; c. Possibilities of active control of burning plasmas. Use of Research facilities JET, AUG, MAST-U, TCV, WEST and COMPASS-U HPC and Gateway (modelling will use the common IMAS framework where applicable) Opportunities for industrial innovation This activity relies on using and advancing the state-of-the-art in diagnostics and control of hot plasmas. Innovative developments in these areas will be tested under real tokamak conditions, and in case of JET, AUG and MAST-U in the presence of high neutron brightness. This can allow for prototyping of technologies that could be used in ITER and DEMO. Fully-digital control infrastructures may be applicable to other fields as well. International collaboration Coordination and support to the participation to the International Tokamak Physics Activity (ITPA) and the participation to the IEA Implementing Agreements in which EURATOM is party. Collaboration on SPI experiments with Korea, US, ITER-IO and on hardware (second injector at JET) EU-US collaboration on DEMO scenarios, in particular on no-ELMs operation Scientific collaborations that need to be developed with ITER to ensure that the Work Programme remains focused on the ITER Research Plan: closer involvement when defining in Page 17 of 143
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more detail the annual work programme; resources for contributing to ITPA Joint Experiments and Analysis when consistent with ITER stated priorities Grant Deliverables Deliverables Table End Date Characterise Helium H-mode access on JET, Comparison with MST 2021 Completion of WEST PEX project Dec. 2021 Install and test multiple shattered pellet injectors on JET to validate ITER’s disruption mitigation 2022 strategy JET: Wide angle bolometry for the exploitation at JET of shattered pellet injectors commissioned 2022 JET: Fast camera for the exploitation at JET of shattered pellet injectors commissioned 2022 Demonstrate ELM control during the transient phases (Ip ramp-up and down, entering and exiting H- 2022 mode etc.) and assess the transferability to ITER and DEMO Quantify the role of the turbulent and MHD driven transport in the vicinity of the separatrix for the 2022 stability of the pedestal and provide theory-based predictions for ITER and DEMO. Demonstrate control of radiative detachment with ITER and DEMO relevant tools 2022 Completion of AUG PEX project Dec. 2023 Completion of MAST-U phase II PEX project Dec. 2023 Establish and compare N and Ne-seeded scenarios in view of ITER seeding gas selection 2023 JET: Laser Induced Desorption Spectroscopy (LIDS) system commissioned on JET 2023 Quantify the role of electron and ion heat channel as well as plasma rotation on the access to H- 2023 mode for hydrogen, helium and mixed plasmas in view of the ITER non-active phase. Report on the physics basis for the decision for an alternative divertor configuration for DTT and 2023 DEMO Install and test laser induced breakdown spectroscopy (LIBS) on JET. Develop and demonstrate in- 2024 situ tritium surface inventory characterisation and removal techniques Assess ammonia production and clean-up for ITER N-seeded scenarios 2024 Recommendation on ELM free high confinement DEMO scenario based on their accessibility and 2024 performance in EU devices. Assess the feasibility to access to ELM free scenario in ITER. Report on the optimisation of plasma performance in stationary MHD stable high βN scenarios by 2024 using integrated plasma control Effectiveness of shattered pellet injection for runaways beam handling in comparison with other 2024 mitigation schemes and provide a stepladder (JET and AUG) approach towards ITER and DEMO. Report on Alfvén Eigenmode stability in H/He/DT plasma and instabilities in DT plasma 2024 Validated integrated modelling of ELM suppression on EU facilities to provide predictive capability 2024 for ITER and DEMO performance and confinement. Quantify the impact of the isotope mix on confinement and pedestal performance in support of DT 2024 operation on ITER and DEMO. Provide an Operational strategy to optimise the access to Q=10 for ITER based on the EUROfusion 2025 experimental and simulation programme. Determine tolerable net erosion and surface damages of plasma-facing components in view of their 2025 lifetime and impact on plasma behaviour in various divertor and plasma configurations. Validated physics models to benchmark conventional and selected alternative divertor 2025 configurations for their differences in transient heat and particle loads and SOL transport Deliver, implement and test an ITER prototype disruption handling system based on physics models 2025 for the most common disruption paths. Validated physics models of fast-ion transport, losses and instabilities against experimental data 2025
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Milestones Milestones Table 2nd NBI system on TCV ready for operation 2021 Cryogenic pump on MAST-U ready for operation 2021 MAST-U achieving KPI for 2nd phase of PEX upgrade 2021 WEST PEX project is operational and ready for scientific exploitation 2021 Implement active profile control with ITER relevant actuators and ITER like PCS concepts 2021 Shattered pellet injection system (SPI) on AUG ready for operation. 2022 JET 2nd SPI and new/improved diagnostics installed in 2021 shutdown and commissioned in 2022 2022 SPI modelling (3D non-linear MHD) for ITER predictions available 2022 JET Active Gas Handling System ready for N2 use 2023 JET scenarios ready for DT operation 2023 New upper divertor (DIV-IIo) at AUG ready for operation 2023 Double beam box on MAST-U ready for operation 2023 ELM suppression workflow ready for validation 2023 IMAS installation completed on all devices 2023 Implement ITER relevant state-observer based multi-machine integrated plasma control tools 2023 Samples of W-based materials foreseen for the 2nd ITER divertor available for plasma experiments 2023 AUG PEX project is operational and ready for scientific exploitation 2023 MAST-U NBI Double Beam Box is operational and ready for scientific exploitation 2023 Integrated SOL and pedestal model available 2024 Integrated workflow for the modelling of fast-ion instabilities, transport and losses 2024 Samples of neutron-damaged materials available for plasma experiments 2024
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02 Exploitation of JT-60SA and Theory-Simulation-Verification-Validation (WPSA) Objectives As outlined in the European Fusion Roadmap, JT-60SA is a crucial facility in support of ITER and DEMO. During the period 2021-2025 (within Broader Approach Phase II), the integrated commissioning of JT- 60SA will be completed, and a set of machine enhancements procured by EU will be delivered, commissioned, and exploited in the 2023 and 2024 experimental campaigns. The main objectives of these campaigns are to mitigate the risks for the first plasmas and the non-activated phase (H/He) in ITER, to further develop ITER scenarios and to demonstrate steady-state high-beta scenarios in view of DEMO. Basic elements, such as L-H threshold, disruption control, ELM pacing, fast particle behavior, will be addressed. In parallel, new machine enhancement projects will be prepared and launched. EUROfusion will participate in all these activities, in close collaboration with F4E. Description of work 1. Participation to the completion of JT-60SA integrated commissioning (2021). 2. Procurement and commissioning of six enhancement systems: cryo-pumps, pellet injection, MGI (massive gas injection), edge Thomson scattering (TS), VUV spectrometry (all in 2021- 2022), FILD (fast ion loss detection) (2023). During the campaigns, participation in systems operation and data production. 3. Preparation of the scientific exploitation of JT-60SA for the 2023 and 2024 campaigns. 4. Development and operation of a Remote Experiment Centre (EU-REC) for participation in the JT-60SA experiments from Europe, in parallel with EU participation on site. 5. Campaign 2023: demonstration of stable operation at nominal plasma current; experiments for risk mitigation of the ITER non-activated phase (H/He); development of ITER scenarios (H- mode, hybrid). Validation of EU codes and models with JT-60SA data. 6. Campaign 2024: experimental study of H-mode and hybrid ITER scenarios; development of steady-state high-beta scenario in view of DEMO. Validation of EU codes and models with JT- 60SA data. 7. Preparation and start of a comprehensive machine enhancement programme for the Broader Approach Phase III (2025-2029). EUROfusion participation should include advanced diagnostics of interest for ITER physics studies and elements of the transition to W-PFC, essential for extrapolation of the JT-60SA results to DEMO. 8. Preparation of a comprehensive scientific programme for the following phase (2025-2029) coherent with the strategic priorities of the EU fusion roadmap. Theory and Simulation development The specific TSVV developments embedded in WPSA are focused on: Advanced discharge simulators, to assist the preparation of EU experimental proposals and enhance their competitiveness. They combine free-boundary equilibrium with plasma transport modules of various levels and will be used to train specific control schemes in advance of the experiments. Breakdown simulators combining free-boundary equilibrium, evolution equations for energy, particles and current and EC beam tracing. Validation on experiments is an essential step. Integrated modelling codes, combining core-edge transport for the various channels (ion, electrons, and fast particles). 3D MHD non-linear codes for the interpretation of disruption mitigation, ELMs and MHD events and able to make predictions towards ITER. Synthetic diagnostic modules, in particular for diagnostics procured and operated by EU Dedicated workflows describing the impact of fast-ion driven instabilities on plasma profiles in a self-consistent way
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Use of Research facilities Use of JT-60SA, by means of participation in the operation, experimental programme, data production and analysis, as well as in programme and campaigns management. Opportunities for industrial innovation Many of the enhancement for WPSA involve industrial procurements, albeit that the larger procurements will be handled via F4E. Grant Deliverables Deliverables Table End Date Appointment of EU Deputy Experiment Leader (after call issued end 2020) Apr. 2021 Final report on Integrated Commissioning. Results and return of experience Dec. 2021 Delivery of Cryo-pump system at Naka Dec. 2021 Report on organisation of the JT-60SA scientific exploitation Dec. 2021 Documented plan of EU enhancement programme for BA Phase III Mar. 2022 Appointment of EU team and validation of EU experimental proposals July 2022 Delivery of MGI, pellets and TS systems at Naka July 2022 Call to start EU enhancement programme for BA Phase III Sept. 2022 Delivery of VUV spectrometry system at Naka Oct. 2022 Delivery and final tests of EU-REC Jan. 2023 Commissioning and calibration of the EU systems before 2023 campaign Mar. 2023 Delivery of FILD system at Naka Dec. 2023 Final report on 2023 campaign. Results and return of experience Mar. 2024 Commissioning and calibration of the FILD system before 2024 campaign Mar. 2024 Final report on 2024 campaign. Results and return of experience Mar. 2025 Delivery of EU procurements (TBD) for campaign 2026 Dec. 2025
Milestones
Milestones Table Reliable plasma operation in H with the initial machine configuration Feb. 2021 Start of the EU-REC project Apr. 2021 Decision on plan and resources of EU enhancements for BA Phase III June 2022 Start of the new EU enhancement projects Jan. 2023 EU-REC tested and ready for use Jan. 2023 Cryo-pumps, pellet system, MGI, TS and VUV ready for operation Mar. 2023 Demonstration of stable operation at 5.5 MA plasma current in H-mode Dec. 2023 FILD ready for operation Mar. 2024 Demonstration of non-inductive scenario at N ≥ 3 Dec. 2024
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03 Exploitation of W7-X and Theory-Simulation-Verification-Validation (WPW7X) Objectives In Horizon Europe, the overall objective of WPW7X is to provide a substantial physics basis for the assessment of optimized stellarators as an alternative line in magnetic confinement fusion. This will be completed with the results from operation with all-metallic PFCs beyond Horizon Europe. Therefore, all activities in terms of experiments, theory and simulation within WPW7X will be oriented to assess the Helical-Axis Advanced Stellarator (HELIAS) line as a reactor concept. Wendelstein 7-X (W7-X) is an optimized stellarator based on the HELIAS concept and is being upgraded to explore new operational domains. In Horizon 2020, the progress reported in W7-X has exceeded the initial objectives, with first demonstrations of optimization concepts and the achievement of detached, long-pulse divertor operation for up to 28s. In Horizon Europe, we will build on this success and address the questions that are critical for assessing the prospects of a stellarator fusion reactor. For this, W7-X is being upgraded to explore unprecedented and previously unattainable plasma regimes in stellarators. Extensions of heating and fuelling capabilities will give access to plasmas having dimensionless performance parameters similar to those expected in reactors. Water-cooled plasma-facing components will allow very long pulse durations to demonstrate quasi-steady-state operation (as long as 30 minutes).
In the EUROfusion roadmap, the assessment of stellarators as an alternative to tokamaks for fusion reactors constitute a hold point expected in the early 2030s and dependent on PFC-upgrade decisions during a period in which ITER is planned to enter its nuclear phase. The hold point critically necessitates:
1. results from W7-X confirming the concept of optimized stellarators,
2. the operation of W7-X with reactor-relevant plasma-facing components,
3. validated theory and simulation tools to extend predictive capabilities,
4. conceptual solutions for 3D-specific reactor engineering (in synergy with WPPRD). A positive outcome will lead to a proposal for a next-step burning plasma stellarator. Consequently, Horizon Europe is the crucial period along the time-line of the European Roadmap to maintain the pace needed to provide alternatives to a tokamak DEMO. Furthermore, WPW7X will deliver contributions to ITER, DEMO and MST devices, particularly through synergistic developments of steady-state technologies and 3-D plasma theory and simulation. International collaborations will be conducted to assess other helical confinement concepts aside HELIAS. WPW7X will continue to contribute to the stellarator databases. In the following, we describe the specific objectives of WPW7X during Horizon Europe. Towards reactor-relevant condition in W7-X: hardware upgrades and scenario development The objective of WPW7X in Horizon Europe is the demonstration of high-performance, steady-state HELIAS operation. W7-X, a first-of-a-kind machine designed on theory-based principles, is the main vehicle for both the experimental programme and the validation of simulation tools implementing cutting-edge 3D plasma theory. Demonstrating quiescent, disruption-free operation at the high plasma beta for a fusion power plant will require a considerable increase of the heating power (ECRH and NBI). More heating power is also needed to demonstrate the positive effect of optimization on confinement at the high temperatures necessary to achieve low collisionality, as in a reactor core. First experiments in W7-X have highlighted the importance of accessing regimes with reduced neoclassical Page 22 of 143
Version 6 May 2020 turbulent transport (e.g. through density profile shaping). The interplay between neoclassical and turbulent transport characteristics of the magnetic configuration with controlled profile shaping scenarios (using a steady-state pellet injector for central fuelling) will be a research focus during this period. The confinement of fast ions is a key objective for 3D magnetic configurations and will be addressed in FP9. The validation of W7-X’s fast-ion confinement properties will be pursued together with the implementation of high-resolution fast-ion loss diagnostics. The theoretically predicted equilibrium and stability behaviour of W7-X will be tested by using the extensive configuration space of the device to vary the expectations over a large range. High-power steady-state operation: qualifying the high-heat-flux divertor and preparing for a metallic wall in Wendelstein 7-X. To demonstrate the inherent steady-state capabilities of stellarators, an actively cooled CFC divertor will be qualified for safe power and particle exhaust. A key objective in Horizon Europe is in fact safe operation at high heating power and plasma beta. To demonstrate high-performance, steady-state HELIAS operation scenarios, heating/fuelling systems will be upgraded, together with safety systems and diagnostics. This work will take advantage of long-term preparations started in Horizon 2020. Reactor-like operation with metallic plasma facing components will be prepared, including a qualification of the relevant strategy and technologies. A decision on the replacement of plasma facing components, and in particular the divertor targets, will be taken. These actions aim at a subsequent implementation of tungsten PFCs, possibly starting at the end of FP9. The foundation for the design of a metallic divertor will be provided by the demonstration of steady-state capabilities with an actively cooled CFC divertor. WPW7X will also build upon synergies with metallic wall developments in WPSA and WPPWIE. Develop and validate theory and simulation tools: understanding W7-X to enable design of the next-step device. The theory and simulation programme in this area will focus on stellarator optimisation along two main interconnected avenues: – Develop and validate numerical tools that accurately and efficiently calculate neoclassical and turbulent transport in multispecies plasmas, linear and nonlinear stability properties of such plasmas, and fast particle generation and confinement, and which are able to predict heat and particle loads on plasma facing components in island divertors. The development of these tools will provide support for Wendelstein 7-X operation, and will support the design and operation of the next-generation of stellarator devices. – Develop new mathematical and computational methods for the optimization of stellarator magnetic configurations. Optimization codes should then be employed to assess the pros and cons of different concepts (quasi-isodynamicity, helical symmetry, quasi-axisymmetry, etc.), and to produce a set of specific magnetic configurations optimized with respect to general plasma physics criteria, including MHD stability, thermal and fast particle confinement and impurity accumulation.
Description of work The campaigns of W7-X in Horizon Europe, about one per year, will be conducted and organized as in Horizon 2020. The preparation of components for heating and fuelling, fast-ion generation, dedicated diagnostics, and the qualification of device operation regimes (e.g. using X3 ECRH heating at reduced field) together with the data analysis and simulation of the experimental campaigns will provide a substantial portion of the work during the various shut-down periods. Given the technical character of the campaigns in the first half of Horizon Europe (commissioning, upgrades), flexibility will be required and a rearrangement of deliverables cannot be excluded. The
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Version 6 May 2020 pace of progress regarding achievement of the objectives will be determined by the level of technical readiness of the device for high-performance and steady-state operation. Leading objectives are arranged in building blocks (as reflected in the list of deliverables below) – the critical path is defined by the readiness of PFC and heating/fueling technologies. For the initial campaigns with water-cooled PFCs (installed by 2021), a progressive commissioning of water-cooled systems leads to a step-wise approach to combine long pulses (target 1800s) and high heating power (target 10MW) operation during the period 2021-28 (cf. time sequence below).
Time line for Mission 8 For the achievement of plasma conditions relevant to optimization studies (low-collisionality, high- beta), heating upgrades (ECRH, NBI) and complementary diagnostics (e.g. multichannel interferometry, edge and fast-ion diagnostics) will be implemented in enhancement projects. Enhancements developed in Horizon 2020 will be operated in Horizon Europe to achieve the W7-X strategic objectives. The preparation of experiments will be accompanied by predictive scenario preparation, benefiting from the close link of experiments, simulations and theory within the same work-package. Metallic wall operation is preprared together with the WP on “Plasma Wall Interaction and Exhaust”, and synergies with other similar initiatives on JT-60SA, DTT, WEST will be explored. Supporting experiments are planned for 2025. Smaller devices will complement aspects of physics studies, and will be used to qualify experimental procedures (e.g. wall conditioning techniques). Theory and Simulation development The development of theory and computational tools (including specific tasks on stellarator optimisation) are an integral part of WPW7X. WPW7X will conduct analysis projects and campaigns to carry out detailed analysis, modelling and scenario development, as well as to exploit and prepare W7-X experiments. The role of theory has been prominent in the initial W7-X campaigns and it is likely that this will continue during Horizon Europe. A number of experimental phases will be largely theory-driven to clarify important physical processes in the device. As an example, initial experiments in W7-X have highlighted the importance of devising operational schemes for accessing reduced turbulent transport regimes, e.g. via density profile shaping. Some amount of turbulence is deemed necessary, however, to avoid impurity accumulation, which is otherwise a serious threat to high-performance operation. Consequently, a theory and modelling effort to improve the understanding of turbulence and the
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Version 6 May 2020 associated transport (particles, impurities and energy) will be of high priority in the coming years. For reduced turbulence regimes at low collisionality, neoclassical transport will often become relevant, so that work on this topic must continue. The quest for higher plasma beta necessitates theory and modelling of MHD equilibrium and stability. Moreover, tools for the predictive modelling and analyses of specific 3D heating scenarios for ECRH, NBI and ICRH require further advancements and their validation is needed for reliable scenario development. Theory tools for fuelling processes – particularly from pellet injection – are also essential for scenario development and for the analysis of high-density, high-performance discharges. All these modelling tools will need to be integrated to enable overall modelling of specific experiments. Other important theory/simulation needs include fast-ion generation and confinement, synthetic diagnostics and edge/SOL phenomena (and neutral plasma) in finite-beta island divertor geometry. Studies of material migration are also needed for the development of next step plasma facing components and for assessing metallic walls as a reactor solution. Since the design of W7-X, enormous progress has been made in the understanding of 3D plasma physics, computer technology and optimization algorithms. For instance, novel multi-target optimization algorithms have been devised with improved parallelization properties and reduced sensitivity to local optima in parameter space. The new or improved codes should accommodate, and further build on, this progress. The overall success of WPW7X will be dependent upon the success of the theory and modelling activities, therefore it is critical that these be assigned sufficient resources for Horizon Europe. WPW7X will support engineering activities integrated into WPPRD aiming at a specification of the technical outline of a HELIAS burning-plasma device, e.g. through the validation of models to be used by systems analysis. Taken together, these theoretical/computational and engineering activities will feed into the stellarator optimization task, aiming to further improve the HELIAS concept. Finally, special attention will be taken to identify and foster synergies with the tokamak research programme. Since a three-dimensional approach is needed to tackle problems in tokamaks once symmetry breaking is accounted for, it is expected that the applicability of theory and codes developed for stellarators will be natural. Use of facilities - W7-X, TJ-II, URAGAN-2M, TOMAS for ICWC preparation - LHD, HSX, CFQS, URAGAN-2M (within International Collaborations). - EUROfusion High Performance Computer Opportunities for industrial innovation Grant Deliverables Deliverables table Year Commissioning of W7-X enhancements 2021 Scenario & campaign preparation (focus: optimization studies, wall conditioning) 2021 Non-linear stellarator gyrokinetic code(s) treating at least entire flux surfaces (not limited to single 2021 flux tubes) First operation OP2.0 without use of water-cooled PFCs (although these are installed) 2022 Scenario & campaign preparation (focus: fast-ion confinement, preparation of steady-state 2022 scenarios) Stellarator optimization code including algorithms with reduced sensitivity to local minima in 2022 parameter space Operation OP2.1 with water-cooled PFCs (energy limit 1 GJ) 2023 Scenario & campaign preparation (focus: turbulent and neoclassical transport) 2023 MHD code(s) capable of rapidly assessing ideal and resistive stability for any stellarator equilibrium 2023 and able to account for the influence of current perturbations Modelling codes for advanced W7-X ICRH scenarios 2023 Operation OP2.2: assessment of fast-ion confinement and high-beta operation (energy limit 2 GJ) 2024 Scenario & campaign preparation (focus: high-power steady-state operation) 2024
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Verified and validated stellarator gyrokinetic codes for the calculation of turbulent transport 2024 Operation OP2.3: High-power, long-pulse operation and assessment of HELIAS optimization (with 2025 data from carbon PFC operation) (energy limit 6 GJ) Scenario & campaign preparation (focus: PFC upgrades and exploitation of OP2.4) 2025 Comparative assessment of the HELIAS reactor physics basis with respect to other stellarator 2025 concepts (with International Collaborations). Modern European stellarator optimization code and its use to determine options for next-generation 2025 devices.
Milestones
Milestones Table ICRH commissioned and 1.5 MW gyrotron infrastructure completed 2021 Plasma operation with water-cooled PFCs 2022 1 GJ energy turn-around achieved 2023 Assessment of the magnetic configuration dependence of fast-ion confinement conducted 2024 High-beta HELIAS operation at low collisionalities 2024 6 GJ energy turn-around achieved (pulse lengths up to 600 s, long-pulse detachment) 2025
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04 Advanced Computing (WPAC) Objectives To implement the European roadmap, in which theory and simulation play a strong role, it is timely and indeed crucial for EUROfusion to develop a coherent programme of Theory, Simulation, Verification and Validation (TSVV). Fundamental research and development are key enablers that must be retained within the programme to advance our understanding and predictive capabilities. These advances will underpin the production of a high quality suite of “EUROfusion-standard” software (building on the research software) to interpret data from ITER and associated facilities, and reliably extrapolate to inform DEMO. To enable the large-scale numerical simulations essential for the programme, EUROfusion will support a dedicated High Performance Computer. This includes support for the centralised integrated modelling computing platform – the so called Gateway. To deliver these outcomes, a higher level of coordination is required that can integrate our world-class fusion science and engineering with emerging advanced computing capability – this is the vision for E- TASC, which stands for the EUROfusion – Theory and Advanced Simulation Coordination, (EUROFUSION GA (18) 24 - 4.6). This fundamental research is performed via a set of TSVV tasks that are in general embedded within the relevant Work Packages. Another key element in the implementation of the E-TASC proposal consists of setting up Advanced Computing Hubs (ACHs) in several host beneficiaries. The ACHs will provide essential expertise and support in computer science, scientific computing, data management, code integration, and software engineering, as well as in the development of a suitable portfolio of EUROfusion standard softwares. WPAC will provide an efficient expert support to users: with respect to code development towards EUROfusion-standard software and adaptation to modern High Performance Computer (HPC) architecture. This includes the provision of high level support for scalable algorithms, code parallelization & performance optimization, code refactoring, GPU-enabling, etc.; for the adaptation of codes to IMAS, the development of Integrated Modelling (IM) frameworks in IMAS as well as plasma/machine control tools; in the area of data handling including the data access and data management of the JET data, open access, data management, data analysis tools, aspects of Artificial Intelligence (AI) and VVUQ. Etc. Description of work Up to six ACHs including the JET data centre will be established in a staged approach from 2021 until 2025, each located within one host beneficiary or within one of its linked third parties, which employs the staff. The ACHs take as input the research outputs from the TSVV Tasks, to develop professional, EUROfusion-standard softwares that are documented, verified and validated, and optimised for ease of use by a wide range of EUROfusion users. Each ACH will be organised around a limited set of specific, fusion-relevant themes in computer science, scientific computing, and software engineering as follows: optimised codes for HPC: scalable algorithms, code parallelization & performance optimization, code refactoring, GPU-enabling etc.); Integrated Modelling and Control: code adaptation to IMAS, IMAS framework development etc.; EUROfusion data including the JET data: data access, data management, data analysis tools, aspects of AI and VVUQ etc. The Technical University of Denmark (DTU) will be in charge of the JET Data Centre that will host all JET data and will ensure that the necessary infrastructure and technical capabilities are available for providing the JET data services during the JET operation (2021-2024) and for 10 years after the end of JET operation. The JET Data Centre
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must be ready for relocation to its final location by the end of 2020. The JET Data Centre includes the arrangements for the long-term storage of and access to JET data and the long- term storage of documents. WPAC is also in charge of the procurement, installation, operation and upgrade of HPC resources for the EUROfusion programme. Currently this programme relies on access to a dedicated part of the MARCONI supercomputer (MARCONI-Fusion) funded by EUROfusion and operated by CINECA in Bologna, Italy with 10 PFlops peak dedicated to EUROfusion in its present phase (2019-2023). A small range platform (the Gateway) for development, testing codes and for integrated modelling is made available on MARCONI as well. The current agreement between EUROfusion and ENEA for the provision of MARCONI-fusion will come to a close in the end of 2023. Looking into the future beyond Marconi-Fusion, while responding to the needs of the European fusion community is essential in order to anticipate the associated technical and financial aspects. An Expert Group to assess the needs of EU fusion community in terms of HPC in the 2023-2028 time frame has been set-up and recommendations have been issued (EUROFUSION GA (19)26-4.10): “EUROfusion should continue its strategy of investment on dedicated computer resources based on medium size systems in order to optimise the resources for its needs and to give a high priority to reliability and availability of these resources”. Therefore, options for providing dedicated high performance computer power to the programme will have to be investigated (2021) and the best solution identified (2022) and implemented (2023). The integrated modelling and control activity will be the fruition of the workflows and data- infrastructure developed under the EFDA task force ITM and EUROfusion WPCD work package. The data infrastructure is now tuned with ITER – IMAS and includes a data dictionary, data structure (IDS), analysis tools, more than 40 codes in IMAS and many released workflows including the European Transport Solver (ETS) all deployed on a single platform: the EUROfusion Gateway. A full set of mapping tools has been developed to write EUROfusion experimental data in IMAS. Key to the joint development is the use of the IMAS infrastructure and tools to share data and deploy device independent modelling tools on the full range of European devices as well as on ITER. Within FP9 there are the requirements of open data for fusion research, and the initial format for data sharing will be proposed to be based on IMAS data dictionary. The integrated modelling and control activity will: 1) Provide continuous integration of the modules in the workflows released within the IMAS infrastructure as they get increasingly used for Tokamak modelling in EUROfusion and take into account changes in the Data Dictionary and computational environments; 2) Develop and maintain tools for mapping of experimental data; porting of codes in IMAS, and providing Kepler and Python actors, Integration of Kepler and Python actors in IMAS workflows including the European Transport Solver, the EQSTABIL, fast-ions, core-edge and synthetic diagnostics; 3) Provide training and support to EUROfusion users of IMAS and workflows for their validation using JET, MST, JT-60SA data and extrapolation towards ITER; 4) Provide users support for the exploitation of the EUROfusion workflows via dedicated Technical Responsible Officers; 5) Develop new workflows to meet the EUROfusion needs of delivering the fusion Roadmap. Use of facilities HPC Marconi-Fusion, and successor. EUROfusion Gateway for integrated modelling. Opportunities for industrial innovation As each ACH will be located within one host beneficiary and given the fact that such an approach is new within the Consortium, industry support will be sought for their setting up as a means to minimize
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Version 6 May 2020 the risk of failure in their implementation. The quest for technical solutions for fusion-specific code integration problems may prove a source for innovative ideas industry would be keen to capitalize on. Grant Deliverables Deliverables Table End Date Initiate and set-up up to five Advanced Computing Hubs including the JET data center 2021 Reach the Key Performance Indicators for the high availability of HPC and Gateway resources in 2021 support of physics and engineering programme Advanced Computing Hubs and JET data center support to the EUROfusion simulation programme 2022 including IMAS exploitation and portfolio of EUROfusion standard softwares for ITER and DEMO High availability of HPC and Gateway in support of simulation programme as set by the Key 2022 Performance Indicators Advanced Computing Hubs and JET data center support to the EUROfusion simulation programme 2023 including IMAS exploitation and portfolio of EUROfusion standard softwares for ITER and DEMO High availability of HPC and Gateway in support of simulation programme as set by the Key 2023 Performance Indicators Procurement and installation of new HPC and Gateway for the EUROfusion programme 2023 Advanced Computing Hubs and JET data center support to the EUROfusion simulation programme 2024 including IMAS exploitation and portfolio of EUROfusion standard softwares for ITER and DEMO High availability of HPC and Gateway in support of simulation programme as set by the Key 2024 Performance Indicators Advanced Computing Hubs and JET data center support to the EUROfusion simulation programme 2025 including IMAS exploitation and portfolio of EUROfusion standard softwares for ITER and DEMO High availability of HPC and Gateway in support of simulation programme as set by the Key 2025 Performance Indicators Milestones Milestones Table Decision on the location of the Advanced Computing Hubs and resources 2021 High availability (defined by KPIs) of Gateway and HPC to EUROfusion users for production runs 2021 Decision on the new HPC and Gateway for the EUROfusion programme beyond 2023 2021 Lists of agreed codes successfully optimized for HPC environment and for Integrated modelling 2022 Installation of new HPC and Gateway for the EUROfusion programme beyond 2023 2022 High availability (defined by KPIs) of Gateway and HPC to EUROfusion users for production runs 2023 Release core-edge IMAS workflow for fully integrated core SOL divertor modelling 2023
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05 Plasma Wall Interaction and Exhaust and Theory-Simulation-Verification-Validation (WPPWIE) Objectives The goal of this Work Package is to implement and coordinate EUROfusion’s strategy on plasma exhaust, as described in Mission 2. Plasma exhaust is a key design element for next generation machines, as increasing fusion output comes at the cost of a more challenging handling of the residual power that needs to be removed at the solid surfaces of the device. The limitations of the materials, still partially unknown in a neutron-rich environment, pose stringent constraints on the possible exhaust solutions, as the predicted unmitigated loads for ITER and DEMO, i.e. the loads that would occur without specific measures to reduce them, may well be beyond tolerable values. This WP aims primarily at Mission 2 of the Fusion Roadmap, but addresses also specific DEMO-related issues (e.g. the impact of neutrons on material properties and associated plasma material interactions) of interest for Mission 3 , and specific HELIAS-related issues (e.g. impact of the complex 3D structure on plasma material interactions) of interest for Mission 8. Large parts of the boundary and exhaust plasma physics still remain unclear. The modifications of the material properties under irradiation still need to be determined quantitatively. To extrapolate present day results to ITER, DEMO and HELIAS with sufficient confidence, adequate predictive capability, based on first principles insight, must be obtained through development of theoretical models and advanced simulations for the plasma edge and for the materials. This needs to be complemented by experimental observations, leading to empirical trends and scaling laws in present day machines. Development of theories and systematic simulation studies in the exhaust area (including plasma and materials) will be carried out within the Work Package, as well as the compilation and critical assessments of cross-machine experimental results. The Work Package will liaise with the Tokamak Exploitation Work Package for the experimental components of the plasma exhaust studies, with specific emphasis on ITER/DEMO applicability, while it will directly drive the theory and predictive simulation effort in this area. For material studies, the Work Package will include theory, modelling and experiments in linear and high heat flux devices. Laboratory experiments, linear plasma devices, high heat flux facilities, and toroidally confined plasmas provide the experimental input and the basis for a comprehensive modelling description of the coupled plasma-surface interactions and plasma exhaust for different magnetic configurations with conventional or alternative divertor. For this WP, a high-level coordination with ITER-IO and the DEMO central design team will be required in particular in the field of plasma exhaust operational scenarios, safety, diagnostics and material migration.
Description of work In the following, the major research themes that the WP will address are summarized.
Plasma exhaust
Both ITER and DEMO will need to operate with a detached plasma, i.e. with a buffer of neutral particles in front of the divertor targets diffusing the power of the plasma and limiting the direct heat flux onto the material walls. A full understanding of how the detached conditions come about and how they depend on the geometry of the divertor is still missing. It will be necessary to clarify the mechanisms of detachment onset, the range of plasma conditions within which detachment is present and controllable, the stability and the depth of the detachment. The two latter concepts are connected to the issue of detachment control with external actuators, required to ensure that the neutral particles
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Version 6 May 2020 do not penetrate too close to the X-point and induce instabilities (MARFEs) or loss of performance associated with a cooling of the core plasma. Passive ways of controlling the detachment front can also be envisaged. As detachment is achieved by seeding trace impurities, issues like the understanding of optimal impurity mix, impurity transport and segregation in the divertor region (to avoid excessive core pollution), the optimization of the radiation and the interaction that they have with the plasma facing units need to be elucidated. The response of the detached plasma to the unavoidable fluctuations of power or density needs to be properly assessed, as detachment burn- through would lead to destructive outcomes at the divertor targets. This problem will become increasingly important as reactor relevant conditions are approached.
Finding viable plasma exhaust solutions is a complex challenge that is not limited to finding a way to reduce the heat fluxes at the target. Other issues need to be investigated in depth, if a reliable reactor solution is to be found. First of all, proper Helium pumping must be preserved even when detachment is achieved and the pressure is reduced at the divertor targets. Failure to do that would result in an accumulation of the fusion ashes and an unacceptable dilution of the fuel in the core. Another critical issue is the protection of the walls of the reactor, which will need to be coated with a particularly thin tungsten layer in order to ensure proper tritium breeding. The walls are subject to a continuous bombardment of semi-coherent turbulent structures called filaments or blobs, which produce an intermittent load of high temperature and density plasma. Learning how to tame the turbulence and avoid high temperature events on the walls will be essential to guarantee a longer life time of the components, especially under erosion (a theme strongly correlated with the material aspects of the Work Package). Equally important will be to assess the relative importance of plasma, neutral and radiation loads on the walls and divertor, whose balance is bound to change in highly radiative and detached plasmas as we move from current experiments to ITER and DEMO. Finally, a very important theme is the interaction of the exhaust solution with core performance. It is already clear from current day experiments (e.g. JET, ASDEX-Upgrade) that the materials surrounding the plasma strongly affect the confinement in the pedestal and hence in the whole machine. In addition, the magnetic and geometric configuration of the divertor and impurity seeding can play a crucial role in determining the overall performance of the device. The understanding of their effect is essential for proper integrated modelling and scenario design. Finally, tritium transport and implantation in more or less remote areas of the machine need to be understood to satisfy nuclear regulations. The development of a tritium housekeeping strategy in long-pulse devices including retention/recovery options is therefore another key objective.
Despite great progress on the subject, it is still unclear whether the baseline ITER exhaust scheme (lower single null, vertical targets, detached conditions) will be transferable to reactors. As a consequence, investigation of alternative options, recently emerged in the community, needs to be carried out. In this context the denomination of alternative configuration refers to any divertor solution that cannot be qualified by ITER and includes, but is not limited to, Double Null, Snowflake, Super-X and X divertors. This Work Package will provide a clear and quantitative assessment of the potential benefit that alternative configurations might have with respect to conventional solutions as far as exhaust performances and core compatibility are concerned, based on the state-of-the-art modelling of the experimental results following the PEX upgrades in the respective EU facilities (AUG, TCV, MAST-U). The uncertainties surrounding the physics of plasma exhaust and its centrality in reactor design require a thorough evaluation of promising alternatives as a precautionary measure to avoid delays in DEMO, if the ITER solution for the divertor could not extrapolate. A focused and time- bound (Dec 2021) subproject will be devoted to delivering a proof-of-principle assessment of alternative configurations for DEMO. The primary activity of the project will be to deliver integrated results through a “loop” where physics and the engineering concepts are synergistically iterated and optimized. The project will deliver an evaluation of the potential benefit that alternative configurations might have with respect to the conventional solution as far as exhaust performances
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Version 6 May 2020 and core compatibility are concerned. The evaluation will be based on numerical simulations carried out with state of the art multi-fluid (SOLPS) and turbulent (e.g. GBS, BOUT++, TOKAM3X, GRILLIX) codes, as well as with experimental results whenever possible (including those from the PEX upgrades, if available). These benefits will be weighed against the unavoidable additional engineering complexity associated with them, which might rule out some of the solutions and lead to an optimized design that the project will identify and recommend. This will include structural calculations for the coils, the generation of 3D CAD designs for remote handling and assessments of neutronic loads and pumping capabilities. As soon as an optimized solution will be identified and developed, it will be handed over to the Fusion Technology Department for further elaboration. Beyond this point, the investigation of alternative configurations will continue in the Fusion Science Department to understand fundamental physics mechanisms of plasma exhaust with the long term aim of optimizing divertor design. Although the project is embedded within the FS Department, the FT Department will be consulted throughout the project on its engineering aspects.
Material science
The understanding of the response and the modification of the materials in the neutron-rich environment of a burning plasma is crucial to the engineering design of fusion machines, and constitutes the boundary condition to the plasma physics studies. As such it plays a crucial role in the integrated system that is a reactor. Qualification of materials and components are key elements of the EUROfusion exhaust strategy. The enhancement projects to support the PEX programme consist also in upgrading a hot cell facility located in FZJ (expected to be completed by 2024): the construction of two new Hot Cells; the setup of a new high heat flux e-beam facility (JUDITH-3); an infrastructure upgrade of the High Temperature Materials Lab (HML) with respect to power supply and cooling facilities; the setup of a new linear plasma device (JULE-PSI) within the hot cells.
Neutron-rich environments, such as ITER, DEMO and HELIAS, produce modifications to the thermomechanical properties of the materials surrounding the plasma. An important objective of the Work Package is the qualification of advanced plasma-facing materials and components, which includes power load testing up to the damage threshold of the ITER monoblocks in high heat flux facilities, and in linear plasma devices with a plasma fluence up 1032m-2 in order to simulate steady- state conditions expected in ITER. Additionally, the impact of large transients such as vertical displacement events on the plasma facing components will be addressed. The qualification of advanced tungsten materials and components for the DEMO divertor and sacrificial protection limiters will be done in a series of high heat flux exposures in GLADIS, JUDITH, QSPA etc. combining steady- state plasma and laser exposition to study synergistic effects. Modelling of melting and evaporation will be carried out. Erosion, surface morphology, fuel retention and material mixing will be investigated for both DEMO and a second ITER divertor. The work will include dedicated studies with fission activated materials exposed to deuterium plasma in JULE-PSI as well as high fluence experiments of full monoblocks in Magnum-PSI and UPP with gas mixtures mimicking actual divertor operations (e-g- D and D+He).
Erosion is a major concern in high power long-pulse devices as it might lead to a reduction of the lifetime of the components and pollution of the main plasma with intrinsic impurities. In particular, the Work Package will model erosion and deposition in ITER plasmas during the application of resonant magnetic perturbations in He and D using state of the art codes (EMC3-EIRENE and ERO2.0). This will allow predicting the outcome of the competition between Tungsten erosion versus prompt re-deposition along the target plate and in particular at the lob interaction zone of the resonant magnetic perturbation in ITER. Erosion under high-Z seeded impurities (required for detachment and core radiation) also needs to be understood.
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A necessary by-product of burning plasmas are the Helium ashes. Helium is known to significantly modify the structural properties of the plasma exposed surface of Tungsten. The impact of Helium operation needs to be assessed, and analysis of Tungsten samples exposed to AUG, WEST and JET plasmas in He and D will be performed to investigate main chamber erosion and surface morphology changes. JET specimens, i.e. PFCs, long-term wall probes including test mirrors and dust, will be analysed in material research laboratories, to characterise dust generation and migration under various conditions. Necessary for this activity is the availability of materials retrieved from JET and of research facilities compatible with handling of contaminated materials. Test of single crystal mirrors and assessment of cleaning techniques will be performed together with measurements of the degradation of optical diagnostic components (together with WPMAT). To address specific ITER-IO issues, structural studies of materials after pre-irradiation and exposure to helium operation will be undertaken.
Dust formation during operation needs to be assessed, as it can cause pollution in the machine, and because Tungsten transport leads to re-deposition patterns and changes in the surface properties. Dust generation under moisture will require laboratory-based experiments on selected materials to improve predictions in the case of water or air leaks into the vacuum vessel. The objective is to improve predictions of dust generation from PFC in case of water or air leaks into the vacuum vessel.
The impact of neutron damage, in isolation and combined with Helium implantation, on the Tritium retention in Tungsten and Beryllium plasma facing units must be investigated and understood. Simultaneously, routes to minimize the Tritium retention or maximize the fuel recovery must be identified. The work Package will address fuel retention and associated issues (permeation and recovery, e.g through baking) for ITER and DEMO materials with dedicated experiments and diffusion/trapping modelling. This will include the determination of the impact of ion-induced damage (pre-irradiation) on fuel retention. The observed synergistic effect of neutron damage and He implantation on the fuel retention shall be analyzed and modeled to identify critical concentrations in Tungsten for the DEMO plasma facing units.
In-situ laser diagnostics will be optimised to assess fuel retention and cleaning efficiency from Be co- deposits and Be-mixed layers in ITER. Laboratory arrangements (e.g. FREDIS for LIDS) will be used to identify the operational window for the diagnostics, in conjunction with in-vessel tests of LIDS on JET. In operando ps-LIBS and ps-LIA-QMS will be developed as tool to monitor the fuel content in ITER and DEMO Tungsten PFCs in vacuum and elevated pressure with He or Ar. Tritium measurements constitute an important part of the material studies for JET (2024).
Common themes (COMMON BETWEEN WHAT AND WHAT ?)
A high-level objective for the Work Package is the validation of numerical tools to simulate and predict advanced exhaust, including 3D PSI codes ERO2.0 and WallDYN-3D developed during Horizon 2020 in JET, AUG, WEST, and W7-X for different plasma regimes and plasma codes like SOLPS-ITER, EDGE2D, EMC3-EIRINE and the fleet of European turbulence codes (e.g. GBS, TOKAM3X, GRILLIX, BOUT++). In addition, the development and qualification of diagnostic tools for in-situ plasma exhaust and plasma surface interaction studies in long-pulse devices is a further key objective.
This WP will also provide scientific support to the transformation of W7-X and JT-60SA from graphite- based to metallic devices, by providing and testing plasma facing components solutions based on tungsten and steel materials, and by providing predictive modelling for the identification of plasma- compatible scenarios, based upon estimates of the Tungsten source strength and of the Tungsten components lifetime. This objective addresses in particular the significance of net PFC erosion, deposition, and dust production in steady-state operation.
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On JET the overall goal is to achieve a comprehensive description of the plasma impact on the modification of wall materials by studying global material migration patterns and fuel retention. The programme aims at analysing the materials retrieved from JET after experimental campaigns using a large set of different analysis methods. The JET specimens (plasma facing components, long-term wall probes including test mirrors and dust) will be studied in material research laboratories to study dust generation and migration under various conditions.
Long-pulse plasma operations in WEST double-null configuration to accumulate high fluence 1027m-2 will be used as reference case for modelling under steady-state conditions. Experiments to study material migration with tracer injection/or tungsten isotope as well as fuel retention and fuel recovery in W PFCs by e.g. isotope exchange D to H or D and baking. The Work Package will also provide complementary tile analysis of WEST ITER-grade plasma facing components.
Theory/Simulation development The specific TSVV tasks that are embedded within this WP are: • Development of a neutral gas kinetics modular code: The EIRENE 3D Monte-Carlo code is used worldwide to model neutral transport in tokamaks with and without magnetic perturbations, stellarator and helical devices. The work would produce a more modern framework for the future of EIRENE, with larger flexibility and usability for the community. • Development of a next generation European Edge and Boundary Code for ITER interpretation and DEMO and reactor relevant devices predictions. The objective is to produce a code able to simulate the physics of the plasma and the neutral particles in the Scrape-Off Layer and in the region inside the separatrix in realistic 3D geometry for various magnetic configurations. The code will include self-consistent cross field turbulent transport and a multi-species approach, relevant reactions and the ability to assess detachment and radiation. Use of Research facilities Linear facilities: Magnum-PSI, PSI-2, UPP, JULE-PSI and within an EU-US collaboration: PISCES- B (until JULE-PSI is in operation) Tokamak facilities: WEST, AUG (Manipulators), MAST-U, TCV, W7-X (Manipulators), JT-60SA, JET, COMPASS-U and DTT. The WP will formulate experimental proposals on European machines in a close collaboration with the Tokamaks and W7-X Exploitation Work Packages. High heat load facilities: GLADIS, JUDITH, QSPA, FE200 Analytical facilities located at various Research Units for materials studies (PFC tiles, test mirrors, wall probes, dust) after plasma exposure: o microscopes, accelerators, implanters, mass spectrometers, surface analysis stations, facilities for tritium measurements, equipment for tile cutting and sample preparation. o access to several analytical facilities for JET will have to be assessed when the level of radiological contamination (tritium and nuclear activation) will be determined depending on the extent of the JET D-T campaign. Opportunities for industrial innovation Development and qualification of advanced tungsten-based materials for high particle and heat load conditions (e.g. in concentrated solar power plants) Detectors development (WHICH DETECTORS?) Predictive modelling of plasma-surface interaction with emphasis on material mixture for coatings (e.g. turbine blade coatings) or material erosion (e.g. air and space industry) Page 34 of 143
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Grant Deliverables Deliverables Table End Date proof-of-principle assessment of alternative configurations for DEMO 31.12.2021 Tile analysis of experiments in W7-X and WEST 31.12.2021 Diffusion and trapping modelling in W PFCs under combined D+He impact and neutron self-damage 31.12.2021 for ITER and DEMO-like conditions. Report on fuel recovery strategies. Optimization of laser-based plasma diagnostics for ITER and other long pulse devices 31.12.2022 Interpretative PSI modelling of material migration and fuel retention in WEST, JET, AUG and 31.12.2022 predictive PSI modelling for W7-X in full W Impact of material damage (pre-irradiation) on fuel retention 2022 Neutral gas kinetics modular code and initial verification/validation 2022 calculation of turbulent transport in the boundary plasma for all conventional and alternative 2023 divertor configurations following the PEX upgrades Damage matrix obtained from the exposition of advanced materials in HHF and plasma devices 31.12.2023 PSI modeling of DEMO main chamber erosion, deposition and fuel retention. Results of PIC modelling 31.12.2023 of the DEMO sheath Recommendation to ITER-IO on Material Research Laboratory on the ITER site (minimum 2023 requirement and auxiliary systems). Comprehensive catalogue on dust in metal devices: generation, migration, quantity, impact of 2023 moisture on dust generation. Properties of JET bulk tungsten and beryllium after extensive test under reactor conditions. 2024 Completion of FZJ PEX project 31.12.2024 Exploitation of experiments (WEST, JET, AUG) related to material migration, fuel retention, and fuel 31.12.2024 recovery including associated modelling High fluence exposition of mono blocks made of advanced tungsten materials in MAGNUNM-PSI and 31.12.2024 pilot-PSI Characterization of plasma-wall interactions in helium for ITER Pre-Fusion Power phase, especially 2024 impact on tungsten Simulation of JET and EUROfusion PEX Upgrades experimental results in view of ITER conventional 31.12.2024 divertor and DEMO alternative configurations. Quantitative comparison of the potential benefit of alternative configurations with respect to conventional solutions as far as exhaust performances and core compatibility are concerned. Install and expose single crystal mirrors relevant to ITER in JET and extract mirror samples for testing 2021 of ITER cleaning technologies on relevant deposits. Compare mono- and polycrystalline mirrors. (installation); 2024 available for analyses Fuel retention studies in self-damaged and neutron damaged materials exposed in JULE-PSI 31.12.2025 Assess LIDS (LID-QMS) by comparison of in-situ and ex-situ examination of the laser-irradiated 2022-24 in-situ; components. 2026 ex-situ Milestones Milestones Table Initial tile analysis of WEST PFUs and W7-X TDU PFCs completed 31.12.2021 Modelling of fuel retention in W under combined D+He exposure and self-damaged W by diffusion 31.12.2021 and trapping completed High fluence experiments in deuterium L-mode discharges in WEST executed 30.06.2022 Incorporation of turbulence results in multifluid calculations using physics based diffusion 30.06.2022 coefficients. Comparative experiments of different LASER-based techniques on W and other reference samples 31.12.2022 executed and level of detection determined Interpretative modelling of W migration and D retention in WEST high fluence discharges completed 31.12.2022 Exposition of initial set of advanced W materials in HHF and plasma devices executed 31.12.2023 3D Modelling of first wall erosion and fuel retention in the DEMO-1 reference scenario completed 31.12.2023 FZJ facility is operational and ready for scientific exploitation 31.12.2024 Exposition of initial set of advanced W PFCs to fluences up to 1030m-2 in MAGNUM-PSI and pilot-PSI 31.12.2024 executed Fuel recovery experiments in WEST executed 31.12.2024 Potential PFCs solutions for an all-W W7-X identified and reference samples exposed in HHF and 31.12.2025 plasma devices executed Exposition of neutron-damaged and self-damaged W samples in JULE-PSI executed 31.12.2025
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06 Preparation of ITER Operation (WPPrIO) Objectives By the end of FP9, ITER will have entered in its operation phase. As ITER is essential for the fulfilment of the European fusion roadmap, EUROfusion needs to be ready to play a leading role in ITER operation to contribute to its success, and, ultimately to benefit from ITER operation and its scientific results in view of DEMO. The EUROfusion roadmap states “To ensure its (ITER) success, a team is needed with deep understanding of the critical plasma issues and equipped with comprehensive validated modelling tools to design and optimise the plasma and its control”. With a growing participation of the EUROfusion members in the preparation of the ITER scientific programme, it is required to increase the integration and coordination of the relevant EUROfusion activities to provide a high level EU input within a dedicated work-package. The WP has three main high-level objectives: 1) To develop the EUROfusion ITER data analysis tools within IMAS for the first phase of ITER operation and design ITER operational scenarios through modelling activities using tools validated on EUROfusion experimental facilities, in close coordination with WPTE; this will provide direct inputs to the ITER research plan; 1) To contribute to the activities of the ITER Neutral Beam Test Facility (NBTF) installed at Padova, which will provide results necessary to optimise the ITER NB system and to define the technical requirements of the procurement arrangements; 2) To improve our knowledge on nuclear technology and safety issues, to validate nuclear codes and to reduce the risks of ITER operations and maintenance activities by taking advantage of JET operation with a mixture of deuterium-tritium leading to the significant production of 14 MeV neutrons. In addition, the WP should provide a high-level coordination and, when necessary, resources for the EUROfusion participation in the International Tokamak Physics Activity (ITPA), ITER fellows activities, ITER operation network, ITER disruption Task Force and future task forces that will be set-up by ITER-IO, Updates of the ITER research plan. In this WP, EUROfusion will act in close collaboration with F4E and ITER-IO. A high-level steering committee will be established, including members from EUROfusion, ITER-IO and F4E. This WP should lay the foundation for a strong and visible EUROfusion participation in the ITER scientific exploitation. Description of work Activity 1: ITER data analysis tools within IMAS for the first phase of ITER operation and design of ITER operational scenarios
Exploit the European Transport Simulator, and the various IMAS workflows in support of the ITER Research Plan in collaboration with the ITER-IO Simulation and Theory group and the international community, Develop ITER data analysis tools including plasma initiation (breakdown, breakthrough,…), wall conditioning simulation tools and synthetic diagnostics for the initial plasma operation; Design operational scenarios for ITER from breakdown to termination while respecting the plant limits (e.g. PF circuits) with free boundary equilibrium and realistic transport;
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including validated sources for heating & current drive, and fuelling. The activity will include development of tools to enable pre-pulse validation on ITER; Design of a Fast Ion Lost Diagnostic (FILD) for ITER: using MSTs, JET and JT-60SA experience to design the FILD for ITER and contribute to the preparation for ITER FILD CDR and PDR.
Activity 2: ITER Neutral Beam System
On 25th July 2019 an Agreement was signed between Consorzio RFX and ITER Organisation for the installation and operation of a test stand for full-size ITER negative ion sources (SPIDER) and a full-size ITER 1 MV Neutral Beam Injection system (MITICA). SPIDER and MITICA are the main two testbeds of the Neutral Beam Test Facility (NBTF) installed at Padova. The Agreement covers a period of 10 years (until 31st May 2030). During Horizon Europe, the main purpose of NBTF is to provide results necessary to optimise the ITER HNB system and to define the technical requirements of the ITER Heating Neutral Beam (ITER-HNB) Procurement Arrangements. It has been agreed that during Horizon Europe, EUROfusion will contribute to the activities of NBTF with 14 ppy/y. This support will be a continuation of the activities started already in 2020. The missions of SPIDER are: To complete the development of the ion source to be used for the ITER neutral beam injectors to the extent that it can meet the ITER requirements; To define the operation description of the ITER source; To develop enhanced performances of the ion sources (e.g. the operation with a minimum beamlet divergence at the current densities required and electron/ion ratios required). The missions of MITICA are: To complete the development of the ITER heating neutral beam injectors to the extent that they can meet or exceed the ITER requirements; To define the operation description of the ITER injector, including the commissioning of the HV and the accelerator and the full beam production, extraction, acceleration, neutralization and transport; To fully characterise the injector performances and to characterise the beam and parameters in H2 and D2. In view of the importance of having smaller and more flexible sources, it was also decided that EUROfusion will contribute during the period 2020-2025 to the scientific exploitation of BATMAN Upgrade (BUG), a 1/8th size ITER-like ion source, and ELISE, a half size ITER-like source compared to SPIDER, both located at IPP-Garching. The two sources are being upgraded to reach long beam pulse conditions. ELISE and BUG activities, supported byEUROfusion with 6 ppy/y aim at supporting the NBTF activities. Activity 3: nuclear technology
In the extended JET programme to 2024 (cf WPTE), it is foreseen that the largest neutron yield will be produced in D-T Experimental Campaign 3 (DTE3) (1.4x1021neutrons) with the neutron yield in D-T Experimental Campaign 2 (DTE2) in 2021 reduced to 0.3x1021 neutrons. All experiments performed in DTE2 will be repeated and extended in scope in DTE3 thanks to the larger neutron production. Moreover, experiments that could not be allocated within the 2020 programme will be performed,
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The key activities in this area are Measurements of the neutron/gamma ray flux, spectra and dose rates at different locations inside and outside the JET biological shield, and comparing these quantities with predictions obtained by nuclear codes and nuclear data used in ITER and DEMO studies (proposed experiments include neutron streaming and shutdown dose rate experiments) (2022, 2023); Measurements outside of the biological shield of the activation of cooling water circulating close to the vacuum vessel (2023): analyses and comparison with simulations using numerical tools used in ITER (2024); Measurements of the neutron induced activation in ITER materials, and comparison with nuclear code and data predictions; measurements of the radiation damage in functional materials used in diagnostics systems (2024); Optimization and testing relating to n/T detectors for tritium breeder blankets (2023); Collection of data on Occupational Radiation Exposure (ORE), and on generation and characterization of waste produced in DT operations (2024); Use of Research facilities - ITER NBTF (SPIDER, MITICA) - BATMAN Upgrade (BUG) and ELISE - EUROfusion facilities in particular JET for the nuclear and neutronics aspects - HPC Marconi-Fusion, and successor, EUROfusion Gateway for integrated modelling Opportunities for industrial innovation n.a. International collaboration Coordination and support to the participation to the International Tokamak Physics Activity (ITPA) and specific ITER Task Forces Scientific collaboration that need to be developed with ITER to ensure that the WP Programme remains focused on the ITER Research Plan: closer involvement when defining in more detail the annual work programme. Grant Deliverables Deliverables Table on Activity 1 ITER simulation End Date ETS ready for interpretative analysis of ITER plasmas 31.12.2022 Predictive simulation of the ITER non-nuclear phase with ETS 31.12.2023 Free boundary simulation of ITER equilibria during the various phases of the operational scenarios 31.12.2024 Predictive simulation of the ITER non-nuclear phase with ETS 31.12.2025 Synthetic diagnostics for ITER first plasma and breakdown simulations 31.12.2025
Deliverables Table – Activity 2- EU participation to the following deliverables End Date EUROfusion participation in the NBTF activities at a level of 20ppy/y 31.12.2021 EUROfusion participation in the NBTF activities at a level of 20ppy/y 31.12.2022 EUROfusion participation in the NBTF activities at a level of 20ppy/y 31.12.2023 EUROfusion participation in the NBTF activities at a level of 20ppy/y 31.12.2024 EUROfusion participation in the NBTF activities at a level of 20ppy/y 31.12.2025 Final report on the test plans and the commissioning and operational procedures of the integrated 31.12.2025 plant I&C and the general I&C systems
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Final report on the test plans and the commissioning and operational procedures of the plant systems 31.12.2025 (cryogenic plant, water-cooling plant, gas and injection systems and the vacuum systems) Final report on the test plans and the commissioning and operational procedures of diagnostics and 31.12.2025 data analysis systems of the test beds Report on the HVPS commissioning and operation plans and the relevant transient and steady state 31.12.2025 analysis Final report on the studies and modeling developed for the Cs operation in the negative ion sources 31.12.2025 Final report on the RF studies and modelling developed for the ICP ion sources for the NB for ITER 31.12.2025 Final report on the beam physics studies and modelling in support of the injector operation for ITER 31.12.2025 Final report on the analysis, design and procurement of the electrostatic mock ups to be installed 31.12.2025 inside the MITICA vacuum vessel
Deliverables Table on Activity 3 nuclear technology End Date Completion of new installations on JET for neutronics/activation experiments and for fuel cycle tests 31.7.2023 Final report on neutronics experiments and validation of nuclear data and codes. 31.12.2025 Final report on analysis of cooling water activation experiment 31.12.2025 Final report on testing of n/T detectors for breeder blankets 31.12.2025 Final report on neutron induced activation in ITER materials 31.12.2026 Final report on Occupational Radiation Exposure and waste data collected at JET in DT operations 31.12.2026 Final report on radiation damage in functional materials 31.12.2027
Milestones Milestones Table on Activity 1 ITER simulation Validation of the ETS on EUROfusion Tokamak operational scenarios 31.12.2021 Validation of the EU breakdown simulation tools on JT-60SA 31.12.2021 Agree with ITER-IO on the ITER synthetic diagnostic to be developed with the highest priority 31.12.2021 Validation of the ETS on JET, MST JT-60SA operational scenarios 31.12.2025
Milestones Table – Activity 2 Completion of the SPIDER upgrade –enhanced driver configuration and pumping systems 30.09.2021 HV testing in Vacuum completed for MITICA 31.12.2022 Assessment of the negative ion current densities in ITER relevant operating conditions, in H/D 31.12.2022 discharges in short pulse operation Integrated Commissioning of the MITICA test bed 30.06.2023 Assessment of the negative ion current densities in ITER relevant operating conditions, in H/D 31.12.2025 discharges in short and long pulse operation
Milestones Table on Activity 3 nuclear technology Completion of measurements of JET nuclear quantities (neutron flux, dose rate, neutron induced 31.12.2024 activation, radiation damage, tritium production rate in a blanket mock-up). Completion of measurements of activation of cooling water on JET 31.12.2024 Completion of n/T measurements with detectors for breeder blankets on JET 31.12.2024 Completion of irradiation of ITER materials on JET 31.12.2024 Completion of testing of DEMO relevant pump on JET facility- AGHS 31.12.2024 Completion of analyses of measurements JET nuclear quantities (neutron flux, dose rate, neutron 31.12.2025 induced activation, radiation damage). Completion of collection of JET data on Occupational Radiation Exposure and waste 31.12.2025
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07 Enabling Research (WPENR) Objectives A far reaching and multi-faceted R&D effort such as that to achieve fusion energy must include, in addition to mission-oriented work, a programme aimed at promoting fundamental understanding, innovation and longer perspective research. Enabling research involving devices funded under the common programme will have to be incorporated into the respective Work Packages, but a separate programme to promote and support fundamental investigations and innovation efforts, all judged on the basis of excellence, will be conducted. Naturally, only topics with relevance for fusion research will be eligible for joint programme funding. In this respect, the Keep-in-Touch activities to the complementary approach of the inertial fusion energy (IFE) are of significance and will be eligible with a maximum percentage of about 10% of the total funding available for Enabling Research. Description of work The process during Horizon 2020 for organising the evaluation of the Enabling Research process was considered excessively laborious and time consuming. Therefore a new, more agile procedure is proposed for the selection of the Enabling Research projects during Horizon Europe. In the new procedure the selection of the proposals will be done by four boards/panels: Proposals in the field of theory and modelling will be handled by the newly established E-TASC Scientific Board; Proposals in the field of technology and developments for the long term will be handled by the Project Board for Prospective R&D; All other MFE proposals will be handled by a special evaluation board, composed of members proposed by the Beneficiaries and with a background in experimental research; For the IFE proposals a specific board with independent experts will be formed.
For all evaluation boards an independent chair is proposed. The relevant Project Leaders and Task Force Leaders act as experts in the boards. They are not directly involved in evaluating the proposals, but will indicate whether proposals have too much overlap with work in the work packages. Additional experts can be proposed to the various boards in case it becomes evident after the call that some competences are not properly covered. Each proposal is reviewed in detail by three members of the board that are exempt from conflicts of interest. They score the proposals in a number of categories, following clear guidelines and with a well described scoring system (in principle the same scoring system that has been used hitherto). The scores of the three members will be compared and any significant discrepancies will be discussed. This will at the end result in a preliminary ranking that will be used to make a short list of proposals that will be invited for an interview with the board. After the interview the scores will be reviewed by the board and a final selection will be proposed to the Programme Manager. As the overall quality of proposals going to different boards may be uneven, a meeting between the chairs of the various boards and the Programme Manager will be held to decide the final budget that is assigned to each category. The Principal Investigators of granted proposals report on an annual basis to their respective board, in which sit the corresponding Project Leaders and Task Force Leaders as experts. This will help maintaining a close connection between the ENR projects and the respective WPs. All granted projects have at the end of their runtime a final report as deliverable describing the main achievements, output and deviations from the originally agreed work plan. On a yearly basis all these reports will be combined into a single report as grant deliverable (starting at the end of 2023, after the end of the first batch of projects).
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Deliverables See table 3.1c Facilities Maintenance and repair of facilities used under this Work Package are to be considered as actions eligible for direct costs.
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3.3 Fusion Technology The Fusion Technology Department (FTD) addresses four programmatic areas: DEMO conceptual design; ; Support to the realisation of IFMIF-DONES; Support to the development of the divertor for the Italian DTT Tokamak, a prototype of the DEMO divertor Coordination of longer-term, prospective R&D, aimed at developing viable advanced technologies, physics scenarios and materials for future fusion power plants. The first programmatic area (DEMO project) will be managed by a DEMO Central Team (DCT) established within the FTD and will be supported by Work Package WPDES. The other programmatic areas will be coordinated by technical Project Coordinators within the FTD in parallel to the DCT (see Chapter 4). DEMO Design Project and DEMO Central Team The Conceptual Design (CD) for DEMO will start in 2021 and will consist of two sub-phases: concept selection of key design and technology solutions for each of the main systems by gate G2 in 2024, and concept design validation to consolidate an integrated system concept design by gate G3, foreseen in 2027. The DEMO plant is a very complex system of systems with a highly integrated architecture, which relies on a large number of sub-systems operating in unison. Designing a DEMO plant presents severe challenges, including: (1) knowledge gaps in key reactor technologies not fully demonstrated by ITER that require further R&D; (2) significant uncertainties in physics and technology; (3) high degree of complexity/system interdependencies; and (4) integration of design drivers across different systems. In parallel with system design/architecture, there is still the need for specific technology R&D. While it is true that the plant design should drive the R&D, the system design and architecture must similarly take into account the readiness of the design/technology solutions considered in order to converge into a feasible architecture on a realistic schedule. The implementation of a clear technology maturation plan for all systems and associated critical technology elements, and a periodical assessment of technical readiness by independent expert panels, including ITERIO, F4E and industry experts, are an essential part of the proposed FP9 activities. To overcome the weaknesses that were identified in the execution of the pre-concept design work in FP8, (e.g., lack of a clear design direction and inefficient design iterations, shortage of skills in system design, plant architecture and nuclear design integration, lack of design authority), a new approach will be implemented in FP9. The DCT is embedded in the FTD to develop and evaluate concepts, architectures, and requirements for the whole DEMO plant. An agile architectural design capability, impartial analysis of options, with quick access to the expertise distributed in the EU fusion research laboratories, universities and industry are necessary to ensure the rapid convergence towards a feasible DEMO plant architecture. The DCT is composed of experienced individuals with technical skills and competences in tokamak design and nuclear plant design and integration. Advanced analysis will be an important part of the design substantiation process using expertise in mechanical design, fluid mechanics, thermal, neutronics and electromagnetics. The DCT is supported by the WPDES, with design-directed activities to be executed in the appropriate EU fusion research laboratories, universities and industry, in a number of technical and management project oversight functions. The DCT Terms of Reference are discussed in Chapter 4. I At least until the completion of the concept selection phase, the DCT will centralise the effort to define the architecture of systems that are critical for the definition of the overall plant and have a Page 43 of 143
Version 6 May 2020 strong impact on its performance. Theses include Plasma, Containment Structures, Breeding Blanket, Divertor, Heating and Current Drive Systems, Magnets Systems (see blue part in Fig. 3.3.1). This architecting work will be managed using an agile methodology. The technology R&D will remain in the Work Packages (WPs) - see green part in Fig. 3.3.1. For a number of systems, with limited impact on the overall DEMO plant architecture, or where the system design competence is primarily in the Beneficiaries, such as Tritium fuelling and Vacuum Systems, Balance of Plant, Plant Electrical System and Diagnostics and Control Systems, the responsibility for the design will remain with the respective WPs. The DCT will work in close collaboration with all WPs (see Table 3.3.1) and organise frequent technical coordination meetings to discuss the evolution of the baseline design configuration, to resolve technical issues and coordinate the interfaces.
Fig. 3.3.1. Schematic showing the organisation of the DEMO development activities
Table 3.3.1. DEMO Project Work Packages Breeding Blanket WPBB BOP & Heat transfer WPBOP Diagnostic & Control WPDC Divertor WPDIV Heating & Current drive systems WPHCD Magnetic systems WPMAG Materials WPMAT Plant Electrical Systems WPPES Remote Maintenance WPRM Safety WPSAE Tritium, Fuelling & Vacuum systems WPTFV 08 Design-assist Activities (WPDES, directed by the DCT) Objectives The WPDES will support the DEMO Central Team (DCT) to advance the technical basis of DEMO in order to arrive to a complete integrated system concept design so that detailed assessments of technical feasibility, reliability, safety, maintainability and costs can be progressively undertaken. WPDES consists of a set of activities, directed by the DCT, to be executed in the appropriate
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EUROfusion research units, universities and industry. For the latter Framework Service Contracts5 will be the preferred mechanism. Fig. 3.3.2 schematically shows the implementation of the work of DCT/ WPDES. WPDES tasks include: Conceptual design tasks Plant Architecture: this includes all system design activities at plant level, in particular cross- functional integration, maintenance, nuclear integration and safety (safety classification concept and overall safety requirements), functional architecture and plant layout System design of critical6 fusions systems: this includes the plasma system, containment structures and architecture driving systems such as Magnet, Breeding Blanket, Divertor Maintenance strategy inside the bio shield including the remote maintenance concept design Architecture, layout and system design of critical conventional systems, in particular the containment structure, the primary heat transfer system (PHTS), ancillary systems, nuclear building & HVAC and waste management System Design for safety specific systems DEMO project support tasks Project Management System Engineering Others Based on industry best practices, the process consists of a series of short exploratory sprint cycles, designed to provide clearer definition of the requirements, obtain better understanding of the associated risks and analyse the identified design solutions. The specific objectives and scope of each cycle are determined based on risk importance. The information obtained from the cycle is evaluated and the risk/benefits of pursuing additional cycles are determined.
5 The services of this Framework Contract will be provided in the form of individual work requests, based on technical specifications that will be the basis of individual task orders. 6 i.e, systems driving the plant architecture and/or poses several issues in term of feasibility Page 45 of 143
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Conceptual Design (CD) Phase & Decision Points
Pre-CD Selection Validation ED preparation Phase
Define and recruit Core team members
Embed Industrial members into team
Define system architecture
Agile team sprints [1]
End of sprint rep.
Architecting/system design activities [2]
Engineering and design activities [3] Concept design of less critical systems
Supporting activities (Project Man. Syst. Eng. ...) [4] Complete integration studies
3D CAD plant model
Plant status yearly update
Initial cost report Updated cost report Cost report
Updated CD Updated CD ED PEP PEP Safety PEP Safety WP support
Safety Analysis
System safety classification guidelines PSAR Develop design codes and design criteria
PCD Gate G1 CD Gate G1.1 CD Gate G2 CD Gate G3 CD review ED preparation
2020 TBD 2024 2027
[1] Sprints categories/topics: (TBD) [3] Engineering and Design Activities (in support architecting [2] Architecting/system design activities: activities): Identify and address technology and/or design solutions Perform EM analysis/Provide expertise in material/Perform limitations of both the technical R&D and the system design/ mechanical analysis/Perform nuclear analysis Identify and compare alternative design concepts/Define [4] Supporting activities (SE, project management, etc.) strategy to temporarily compensate for uncertainties, i.e design Coordinate technical reviews/Identify and address any missing margins, fall back alternatives, perform sensitivity analyses/ requirements/Provide configuration management tools and Perform (as part of sprint) system design of the critical system procedure to include the establishment of baseline management and in particular Identify the dominant requirements and (key project documentation)/Define SE method and tools and constraints/Define Safety Design Strategy, perform Preliminary provide support to core team and WPs/Define project Hazard Analysis, Risk and Opportunities Assessment, and CD management (incl. project control) procedure and tools and Safety Report provide support to the core team and WPs/Organize team selection, training, knowledge management
Fig, 3.3.2 Schematic diagram showing the implementation of the work of DCT/ WPDES
Description of work The Work Breakdown Structure (WBS) for WPDES can be seen in fig. 3.3.3. A description of the scope and content of each of these WBS elements will be documented, like in other WPs, in the Project Execution Plan (PEP). As explained before (and illustrated in figure xx below) the schedule will be organized with (a) “sprints” and (b) intermediate gates to freeze selected elements of the architecture.
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Plant Plant architecture including integration, in particular building architecture layout and transverse function (eg. safety, maintenance, etc.)
Fusion System design of critical fusion systems (e.g. breeding blanket, systems magnet system, plasma system, divertor, etc.)
Conceptual Conventional System design of conventional systems driving plant Design tasks systems architecture (eg. nuclear buildings, etc.)
Maintenance System Design of remote maintenance systems systems WPDES Specific safety System Design of specific safety systems (e.g. VVPSS) systems
Project Project management tasks including cost and budget control, Management plant cost estimation & scheduling Phase System System engineering tasks including interface and requirement independent/ Engineering management, configuration management, etc. support tasks
Others Fig. 3.3.3 WBS of DCT/WPDES activities A number of elements for Work Breakdown Structure (WBS) are identified, as described below, but it has to be noted that these are subject to expansion or changes as the conceptual design progresses. [OTHERWISE, WHY ARE WE SAYING THAT THESE ARE NOT EXHAUSITIVE NOR BINDING ??] Plant Architecture Setup a global DEMO system analysis to serve as basis of all engineering work. Perform plant global analyses (structural, thermohydraulics, neutronic, etc.) and provide the resulting specifications for all WPs. Support the sub-systems to perform proper system analysis to define clear boundaries of the systems, functions, decomposition of the sub-system into sub-sub-systems or components, states of operation, etc. Define the DEMO operational phases. Define the propagation of plant requirements to level 1 systems. Management, analysis and control of requirements. In particular, develop a traceable design of system from the high level ‘Stakeholder’ requirements down to the component requirements. Preparation and maintenance of DEMO high-level technical documentation. Define and implement plant layout principles, manage space reservation/envelops models of all level 1 systems, setup and administrate a central digital mock up, manage tolerances chain, manage maintenance/assembly space reservation. Cross functional integration engineering activities, in particular ensure maintainability of the plant, nuclear integration and safety; this includes advanced analysis in mechanical design, fluid mechanics, thermal, neutronics and electromagnetics. Fusion Systems System design of all systems that affect the plant architecture (i.e., superconducting magnets, breeding blanket, divertor, etc). This is not intended to cover the detailed design and analysis of the individual systems, as this work will be conducted in the WPs. System Design activities entail: Definition of the system requirement (propagated from plant level, taking into account the technical performance of the envisaged technologies). Management of interfaces with other systems at level 1 and with plant transverse function. Management of the physical integration of the system inside DEMO. Page 47 of 143
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Definition of the functional architecture of the system. Definition of the logical architecture of the system (sub-systems). Propagation of the requirement at system level. Layout and/or envelop models of the sub-system. Management of the internal interfaces. Selection of relevant technologies for the various sub-systems (link with the tech. R&D program, i.e., WPs). If relevant, management of the variants. Analysis to verify the fulfillment of the system “constraints” (or loads); this requires advanced analysis expertise in mechanical design, fluid mechanics, thermal, neutronic and electromagnetics. Risk management including detailed studies of main technical risks. Conduct studies, as required, of alternative plant or system design concepts and assess their attractiveness against the reference baseline concept. Support trade-off studies for the selection of attractive variants. Interplay between plasma physics and fusion systems Definition of criteria for the selection of DEMO plasma confinement mode (e.g. H-mode, I- mode, L-mode…). Oversight and liaison of plasma testing within the fusion community to support proposed scenarios in view of their power plant application. Definition of the plasma control strategy for planned and accidental operation. Identification of the requirements in terms of diagnostics, H&CD auxiliaries and control coils to prevent plasma wall contact and disruptive events in general. Divertor – stability of the detached condition and assessment of diagnostics and actuators for the mitigation of reattachment risk. Ensure efficient particle exhaust pumping, with particular attention to the avoidance of He accumulation in the core. Definition of thermal loads specifications on the first wall during regular operation and off- normal transients. Determination of required physical quantities for safety-related assessments – e.g. D and T fluxes on the first wall for the evaluation of W erosion, tritium retention and permeation, etc. Necessary power and injection position for each of the relevant H&CD function during all discharge phases – flat-top, planned and unplanned transients. Assessment of He transport for the dimensioning of the pumping system. Determination of the necessary seeded impurity fluxes to ensure divertor protection. Determination of the expected steady-state fusion power level. Conventional systems This includes: Containment structures, include the Vacuum Vessel, Thermal shields and Cryostat structure. Primary heat transfer system (PHTS). Waste systems: System engineering/requirements, design and if necessary analysis of waste considering also accident scenarios. Define on-site waste storage and processing facilities. Civil engineering: Sub contract with industry to complete civil engineering of nuclear building designs. Cryogenic system: Sub contract design of cryoplant and cryogenic systems. Ancillary Fluid systems: System engineering/requirements, design and if necessary analysis of the following systems: HVAC both nuclear and non-nuclear system/Compressed air/Hydrogen monitoring/Liquid and gas distribution systems/demineralised water.
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Fire systems: System engineering/requirements, design and if necessary analysis of fire monitoring and suppression system. Input to/aid design of civil structures, such as thickness of walls, zoning and partitioning. Instrumentation and controls: Define preliminary instrumentation standards for all systems and instrumentation architecture for whole plant, integrate all proposed instrumentation across plant and liaise with layout to define routing.. Maintenance System Support maintenance integration to ensure the proposed DEMO architectures, defined in the Concept Phase, will be feasible and capable of being suitably maintained Safety Integration Based on ITER and EPR experience there are likely to be a number of specific safety systems within the DEMO plant. The majority of these systems will be managed within the relevant WP. However, the ITER and EPR experience also highlighted the need for additional safety system(s), which do not fit within the existing WPs. These systems have yet to be determined and will be identified in the concept phase. The safety system WBS element is a place holder for the expected work to support the transverse function safety. Support tasks Besides the system design and architecture missions described, the DCT has an important role of technical coordination and follow-up of the work performed in the work package, to ensure that the tasks performed there are in-line with DEMO architecture needs (coordination of the tech. R&D and system design) and also to ensure a proper quality of the deliverables (documentation following industry standards and best practice, knowledge management, etc.). Project Management Additional industrial project management support to provide consultancy support and guidance utilizing best practice methodologies. Management of the budget and reporting of the spent. Management and oversight of task specifications and grant. Continuing cost estimation support to enable evaluation of the proposed architecture as part of the selection process. Scheduling support to provide regular updates of the DEMO integrated schedule. System Engineering It is important to define and implement a global system engineering approach early in the Conceptual Design phase, without going too much into the details, to identify the architecture drivers and the main requirements, having tools and procedures to manage the design process complexity, adopting a systematic approach and analysis methods to avoid missing key requirements or constraints. The DCT will be strengthened and composed of experienced engineers, able to manage the complexity of their systems. System engineering skills are required in DCT and WPDES in order to support the system design and architecture activities taking place in all WPs. The proposed system engineering approach for the CD phase will focus on some key procedures (interface and requirement procedures) and few models based system engineering (SE). In addition, basic configuration management principles will be implemented. The corresponding deliverables include: Some selected guides (about requirement management, interface management, etc.). Support in the applications of the principles and documents described in these guides.
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Review of system engineering deliverables. Tools and databases to support the procedure (in particular to ensure the traceability from the high level ‘Stakeholder’ requirements down to the component requirements). Depending on available resources in the labs, a selected MBS method and tool. QM processes and supporting tools Project Management and SE will collaborate in the definition of the DEMO Quality Management (QM) processes together with the implementing IT tools. For the support of the CD phase, the following actions are required: Find an ad-hoc implementation of an agile methodology. One challenge is in particular the variants and change management, where appropriate methods and tools should be found to reconcile the two contradicting requirements: needed flexibility to investigate different architectures, and required rigor in the definition of the configurations. Start the implementation of the PLM (Product Life Cycle Management) - critical to manage 3D design data across 27 sites and integral for configuration management (management of technical baseline). As needed, other IT: electrical design software, Primavera and DOORS etc. In preparation of the Engineering Design (ED) phase, further actions are required: Additional process and procedures required for the ED phase. Applicable codes and norms. Standard parts catalogues (to the appropriate level).
Grant Deliverables ID Deliverable Date Project Change Dossier - 2021 record 2021 Project Change Dossier - 2022 record 2022 Project Change Dossier - 2023 record 2023 Project Change Dossier - 2024 record 2024 Technological Baseline 2024 (incl. for instance plant requirements, plant architecture & layout, system 2024 level 1 architecture, etc.) Project Performance Baseline 2024 (incl. a project execution plan, a risk register and additional 2024 document like cost estimate, etc.) Management Baseline 2024 (incl. preliminary system engineering and PM procedures) 2024 Project Change Dossier - 2025 record 2025 Project Change Dossier - 2026 record 2026 Project Change Dossier - 2027 record 2027 Technological Baseline 2027 (incl. for instance plant requirements, plant architecture & layout, system 2027 level 1 architecture, etc. Project Performance Baseline 2027 (incl. a project execution plan, a risk register and additional 2027 documents like cost estimate, etc.) Management Baseline 2027 (incl. full set of Quality Management procedures) 2027 Product Life Cycle Management (PLM) Platform 2027 Ad-hoc meetings of the DEMO Design Authority (DDA, see Chapter 4) will be organized, in order to validate decisions at plant level. Every decision of the DDA that will require a modification of the baseline (e.g. down-selection of a variant, selection of an architecture) will be recorded (as in the change management procedure) in “Project Changes Dossiers”. These consist of: the original request (depending on the “sources”, either a Project Change Request, a Deviation Request or a Non-conformity Report), the impact analysis, the rationale for decision by the DDA, Page 50 of 143
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the list of baseline modifications (documents to remove, to update and to insert, in which Baseline Dossiers), all new documents (or new versions of the document) to be inserted or updated in the updated baseline. Every year, a record of all “Project Change Dossiers” will be edited and delivered by DCT which facilitates a yearly follow-up of the main decisions.
Grant Milestones ID Milestone Date Incremental Gates G1.1, G1.n (as defined by CCB1, see Chapter 4) TBD Gate G2 2024 Gate G3 2027
International Collaboration Country Description of Collaboration n/a
Industry Name Description a DEMO complex civil design & layout, selected buildings & systems a Safety Analysis a Tools for agile design methodologies a Plant systems & geometrical integration services a Cost estimation services a Configuration management services a Safety & licensing support a Design of conventional buildings & HVAC a System design (cooling water, safety & convent. systems) a Design of Safety I&C concept a Maintenance strategy concept inside bioshield b Support engineering analyses b Development of port closure plate sealing concept b Conceptual design of the Vacuum Vessel b Design office services to support the central team b Cryogenic Plant and Cryo-distribution Systems b Project management and system engineering support, knowledge transfer and guidance utilizing best practice methodologies b Set-up and configure a PLM system a. Activities foreseen to be part of the Framework Contract with Industry b. Activities foreseen outside of the Framework Contract
Use of Facilities Facility Status Scope of Use Year Name (New/Upgrade/Commissioned) n/a
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Main Risks Risk Description Risk Impact Mitigation Strategy Unable to establish DCT Major None without modifying consortium agreement Lack of commitment to WPDES Major None without modifying consortium agreement Lack of commitment of RUs to execute R&D priorities Major None without modifying consortium agreement Tech. R&D not aligned with new design solution Major None without modifying consortium agreement Difficulties in securing industry involvement Major None without modifying consortium agreement Lack of adherence to new governance Major None without modifying consortium agreement
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09 Magnet System (WPMAG) Objectives The primary objective of the work package Magnet Systems (WPMAG) is to deliver a feasible, integrated concept design of the DEMO Magnet System. This entails three main actions: Develop the advanced design of the magnet system and its mechanical structures, following the design baseline evolution of the DEMO fusion power plant. Develop the concept design of the auxiliaries systems (cryogenic plant and distribution, quench detection system and interface of the fast discharge units with the magnet system and feeders). Demonstrate the feasibility and down-selection of the toroidal field (TF), central solenoid (CS) and poloidal field (PF) winding pack (WP) proposals to one main option and possibly a back- up option by Gate Review G2 in 2024. Validate the selected winding pack proposals by Gate Review G3 in 2027. Description of work
WPMAG R&D G2 G3 2021 2022 2023 2024 2025 2026 2027
Sub-scale TF conductor samples testing
Conductor Conductor development Goal: Design optimization for concepts TF winding pack/ conductor selection Full-scale TF conductor samples testing Full-scale TF conductor samples testing Goal: Performance evaluation of concepts Goal: Evaluation & validation of concept TF R&W bending test Goal: Demonstrate & validate performance under bending
Full-scale PF conductor samples testing PF winding pack/ Goal: Performance evaluation of different concepts. conductor selection
( Joints concept selection LTS Development of joints for TF, PF & CS coils for risk identification Joint development TF, PF & CS coils for risk identification
Goal: Joints design & manufacture evaluation. Goal: Joints design & manufacture validation & &
HTS CS winding pack/ conductor selection Sub-scale CS conductor
) Full-scale CS conductor samples testing Full-scale CS conductor sample sample testing Goal: Performance evaluation of concepts Goal: Performance validation of selected CS concept
Goal: Concept optimisation Complimentary Complimentary
demonstration Insulation system selection technology technology Small sample insulation tests Large-scale insulation test Goal: Evaluation of innovative insulation systems Goal: Validation of selected insulation system
Longitudinal welding dev. Goal: Demonstrate industrial-
scale He tight welding
& &
manufacturing
HTS long HTS lengths long Demonstration R&W 100m conductor Goal: Industrial manuf. Process and QA
HTS 50m conductor (
LTS Goal: Industrial manuf. Process and QA
)
Pilot plantPilot
facilities & &
new EDIPO facility rebuild Manufacturing & testing of the insert coil demonstrator Goal: Commissioning of EDIPO facility Goal: Validation of demonstrator in operating conditions
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WPMAG Design G2 G3
2021 2022 2023 2024 2025 2026 2027 TF
Cost assessment for all designs , ,
CS Goal: Manuf. & ops. costing & &
& & Integration of multiple design variants Detailed studies & optimisation PF Conductors Conductors PF
Coils Goal: Development of design options for efficiency & robustness studies Goal: Detailed design & optimisation of selected conductors
Assembly studies of magnet system Goal: Prep. & investigation of assembly steps & sequence
Evaluating RAMI studies Detailed RAMI studies Goal: Initial RAMI studies of all design options to support selection Goal: Detailed studies of selected system
General thermal-hydraulic analysis of design options Detailed thermal-hydraulic analysis of selected option
Analyses Goal: Evaluation of thermal-hydraulic performance of conductor concepts Goal: Optimisation of performance for selected concept
Initial mechanical analyses Refining mechanical analyses Goal: Initial analysis of coil designs & detailed analysis of sub-systems Goal: Detailed analysis of selected concept & integration
AC loss tools AC loss optimisation studies
Goal: Further development of AC loss predictive tools for cable geometries Goal: Reducing AC loss of selected conductors
Auxiliary systems
Initial conceptual design of auxiliaries Overall conceptual design of auxiliaries Goal: Design of critical components for cryogenics, quench detection & feeders Goal: Design of cryogenics, quench detection & feeders
Grant Deliverables ID Deliverable Date MAG R&D PEP7 2021 TF R&W bending performance report 2022 Industrial scale longitudinal welding development report 2022 Performance evaluation report on the TF conductor concept & down-selection 2024 Report on the manufacturing of the 100m long R&W conductor sample 2024 Report on the manufacturing of the 50m long HTS conductor sample 2024 Performance evaluation report on the CS conductor concept & down-selection 2024 Performance evaluation report on the PF conductor concept & down-selection 2024 Performance evaluation & manufacturing report for the down-selection of joints 2024 Performance evaluation report on the insulation systems & down-selection 2024 Technology validation report for TF/CS/PF conductors, joints & insulation concepts 2027 Technology validation report on the insert coil concept 2027
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Grant Milestones ID Milestone Date Manufacture & test of sub-scale superconducting samples 2022 EDIPO facility rebuild - main EDIPO coils wound 2022 Bent TF WP#1 samples manufactured & tested 2022 Manufacture of joints 2023 Manufacture of full-scale superconducting samples 2023 TF conductor concept selection 2024 Manufacture of 100m of R&W Nb3Sn conductor 2024 Manufacture of 50m of HTS conductor 2024 CS conductor concept selection 2024 PF conductor concept selection 2024 Joints concept selection 2024 Insulation system concept selection 2024 Full-scale manufacture & test of selected concept conductor samples 2027 Manufacture & test of selected concept joints 2027 Manufacture & test of insert coil 2027 Manufacture & test of large mock-up arrays of SS jacket insulated and impregnated 2027 Magnet system conceptual design validation 2027
International Collaboration Country Description of Collaboration
Japan Test of the insert coil to be made of a R&W Nb3Sn conductor and/or a HTS conductor, inserted into the existing CS model coil in Naka, Japan. South Collaboration with the Korean K-DEMO based on Nb3Sn TF coils and mechanical analysis of the magnet Korea system. Exchange of ideas, experience and other technical challenges related to the magnet system. USA Collaboration with MIT developing SPARC tokamak made of HTS magnets based on REBCO conductors. Exchange of ideas, experience and other technical challenges related to the HTS conductor manufacturing, the issue of performance degradation during cyclic loading and HTS cable modelling. Undefined Manufacturing and test of mock-up arrays for insulation
Industry Name Description Tratos Cavi, IT Conductor cabling Criotec, IT Conductor manufacturing GE, FR and/or ASG, IT Manufacturing of the Insert coil Undefined Manufacturing and test of mock-up arrays for insulation
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Use of Facilities Facility Name Status Scope of Use Year (New/Upgrade/ Commissioned) SULTAN (SPC, CH) Commissioned Electrical tests for LTS and HTS full-size conductors and joints in fields up to 10.9T EDIPO (SPC, CH) Upgrade Electrical tests for LTS and HTS full-size conductors and joints 2021- in fields up to 15 T 2022 FBI (KIT, DE) Commissioned Electromechanical tests for HTS sub-size conductors JOSEFA (CEA, France) Commissioned Electromagnetic tests on sub-size conductors and joints PACMAN (Twente, NL) Commissioned Electrical tests for LTS and HTS strands TWENTE PRESS (NL) Commissioned Electromechanical tests for LTS and HTS conductors JOSEFA (CEA, France) Commissioned Electromagnetic tests of sub-size conductors and joints BERENICE (CEA, FR) Commissioned Electrical tests for LTS strands OTHELO (CEA, FR) Commissioned Hydraulic tests for LTS and HTS conductors THETIS (IPPLM, Poland) Commissioned Hydraulic tests for LTS and HTS conductors CSMC (Naka, Japan) Commissioned Electrical tests of the insert coils (long samples)
Main Risks Risk Description Risk Impact Mitigation Strategy Show stopper identified in a coil design TF or CS coil could not be built with the Keep a back-up solution for the preventing successful coil manufacture selected solution/technology TF and CS coils SULTAN test facility is damaged TF and CS conductor prototype samples Support upgrade of the EDIPO could not be tested in operating conditions test facility
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10 Breeding Blanket (WPBB) Objectives The objective of this WP is the development of the Breeding Blanket (BB) System for DEMO, including the Breeding Blanket sectors (BBS) and the associated Tritium Extraction/Removal system. The specific steps to reach this objective during the Conceptual Design phase are: Concept selection studies for Driver and DEMO Test Blanket Selection (2021-2024). The Helium-Cooled Pebble Bed (HCPB) and Water-Cooled Lithium Lead (WCLL) concepts will be further investigated, critical R&D completed and integration aspects clarified in relation to the possible DEMO plant architecture. This will provide a sound basis for the selection of a driver and test blanket in 2024. Validation of the BB system for the CD of DEMO (2025-27). Completion of the conceptual design of the driver and test blanket systems to be adapted to the selected plant architecture. Supporting R&D programme to validate the proposed design performance and increase the technical maturity level. This applies to critical technologies such as T-permeation/corrosion barriers, tritium extraction methods, fabrication and qualification of breeder and multiplier materials, and development and validation of alternative lower cost routes of fabrication for structural elements of the BB. Support the ITER TBM (Test Blanket Module) programme in preparation of the preliminary (2022) and final (2025) design reviews, as well as the procurement phase for the first TBM (2026-2027). WPBB will carry out the R&D programme jointly for DEMO and TBM in key topics of the ITER TBS (Test Blanket System) development. It will support the breeders and neutron multipliers procurement of the first TBM set.
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Description of work
WPBB-TBM R&D G2 G3
2021 2022 2023 2024 2025 2026 2027 breeder
development Production & characterisation of advanced CB pebbles (unirr.) Optimisation of CB pebbles in continuous process (unirr.) Ceramic Ceramic
G2: blanket selection and TBM FDR ( CB Irrad. rig design & Irradiation of pebbles to 2-3 dpa Post-irradiation pebble examination Procurement roadmap & ) ) construction
MPH for BB concept design development
Be Production & characterisation of advanced multiplier materials Transfer to industry production
-
multiplier
( BM
G2: blanket selection and TBM FDR ) ) Irrad. rig design & Irradiation of multiplier to 2-3 Dpa Post-irradiation examination construction Procurement roadmap & MPH for BB concept design
T extraction testing in PAV & GLC T extraction in integral PbLi loop testing
PbLi PbLi Goal: Selection of T extraction technology Goal: Validation of selected process development
WCLL T extraction tech selection PbLi extraction syst. concept design
–
technology PbLi purification technology development Integrated PbLi purification system testing Goal: Performance test of technologies Goal: Validation of selected process Performance data & component dimensioning PbLi purification syst. concept design MHD testing in MEKKA & MaPLE MHD tests in MEKKA, MaPLE & high magnetic flux facility Goal: development of database & predictive tools Goal: development of database & predictive tools MHD design of the WCLL WCLL concept design contirbution
technology EUROFER in water tests: H embrittlement, stress corrosion cracking, cooling cooling Water Water corrosion fatigue, environmental assisted cracking WCLL water Goal: database created Water coolant system chemistry definition concept design Radiolysis testing Integrated testing of WCLL water chemistry
Goal: definition of reference water chemisty Goal: Validation of selected processes
thermohydraul Helium HCPB breeding zone testing for for HCPB Goal: Hydraulic performance qual.
HCPB thermo-hydraulic - cooling cooling HCPB manifold testing concept design Goal: Hydraulic performance qual. HCPB FW testing
. . Goal: Hydraulic performance qual.
thermohydraul Water
for for WCLL WCLL breeding zone test WCLL thermo-hydraulic
Goal: Hydraulic performance qualification concept design
- cooling cooling WCLL manifold test WCLL FW test
Goal: Performance qualification Goal: Performance qualification
. .
dev
barrier EUROFER coatingEUROFER
. . ECX, PLD, ALD fabrication, Testing & selection of reference technology Industrialisation & testing of reference technology
at PbLi at contact as Goal: Validation of selected process & &
T DEMO reference coating tech. selected
- permeation Irrad. rig design & Coating irradiation to 2-3 dpa Post-irradiation coating examination construction BB conceptual design manuf. route and definition
manufacturing Development of EUROFER manufacturing technologies incl. FW W coating
technology Goal: Feasibility of BB manufacturing technologies Blanket Development of WCLL specific manufacturing technologies Blanket section reference BB conceptual design fabrication Goal: Feasibility of BB manufacturing technologies manuf. route & tech route and tech. definition Development of HCPB specific manufacturing technologies Manufacturing & test of fabrication mock-ups (TBM scale) Goal: Feasibility of BB manufacturing technologies Goal: Qualification of BB manufacturing technologies
HELOKA/KATHELO Facility test Goal: HCPB testing ready
Large water loop design & construction Facility test ready
Goal: WCLL large mock-up testing New New Facilities WCLL breeding zone loop Facility test ready Goal: WCLL PbLi/water testing HCPB TER conceptual design Purge gas testing facility: design & construction Integral out-of-pile HCPB purge system Goal: Integral test of HCPB purge gas technology Goal: Performance qualification test WCLL TER conceptual design PbLi loop testing facility: design & construction Integral out-of-pile WCLL PbLi loop Goal: Integral test of WCLL PbLi loop technology Goal: Performance qualification test Procurement of CB for HCPB TBM Ceramic production pilot plant: design & construction Production tests Procurement for HCPB TBM Goal: TBM procurement Goal: Pebble qualification Goal: CB pebble procurement in ITER
WPBB WPBB + TBM TBM
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WPBB Design G2 G3 2021 2022 2023 2024 2025 2026 2027
HCPB System Engineering (SE) studies Goal: Baseline definition for comparison Design comparison studies BB baseline selection
& & WCLL/HCPB design development Goal: BB baseline selection for DEMO support documentation
WCLL BlanketWCLL Goal: Reference technology selection BB conceptual design SE studies baseline documentation
Design Goal: Def. for comparison Design comparison studies WCLL/HCPB design dev Goal: BB baseline selection Goal: Ref. tech. selection
& & Adaption of system design to DEMO Definition of reference system Reference system conceptual design validation
TER TER baseline design for selection Preliminary conceptual Reference conceptual design Conceptual design for the design for the defined system for the defined system defined system for DEMO
Grant Deliverables ID Deliverable Date BB.M.D1 BB R&D PEP8 Jan 2021 BB.T-D1.4.3.1 Report of HCPB TBM getter beds performances under T Nov 2021 BB.T-D1.4.3.2 Report of HCPB TBM HYDREX experiments Nov 2021 BB-T.D2.2.1 Report on performance results of TBM GLC tests in TRIEX-II Nov 2021 BB-T.D1.2.1 Report on Industrial procurement of Hex-Beryllide rods Nov 2022 BB-T.D1.3.1 Report on ACB-ABN Irradiation rig design, construction and commissioning Nov 2022 BB-T.D2.4.3 Report on test results for the out-of-pile characterization of WCLL TBM Coating Nov 2022 BB.T-D1.3.2 Report on irradiation in fission reactor of ACB-ABN samples. Nov 2023 BB.T-D2.2.2 Report on assessment and selection of reference T extraction technology for WCLL in Nov 2023 DEMO BB.T-D2.3.1.1 Report on Assessment of Hydrogen Embrittlement, Stress Corrosion Cracking, Nov 2023 Corrosion Fatigue and Environmental Assisted Cracking for water cooling in WCLL BB.T-D2.3.1.2 Report on Radiolysis studies with definition of a reference water chemistry in WCLL. Nov 2023 BB.T-D2.5.1 Report on comparison and selection of PbLi purifications technologies for WCLL TER Nov 2023 Design. BB.T-D1.2.2 Report on chemical, mechanical and thermal characterization of Beryllide rods as ABN Jun 2024 for HCPB blanket in DEMO. BB.T-D3.1.2.1 Report on a preliminary assessment of manufacturing technologies and assembly Jun 2024 routes for the HCPB blanket BB.T-D3.1.2.2 Report on a preliminary assessment of manufacturing technologies and assembly Jun 2024 routes for the WCLL blanket BB-S-D.G2.DEF G2 Definition Dossier Nov 2024 BB-S-D.G2.JUS G2 Justification Dossier Nov 2024 BB-S-D.G2.PER G2 Project Performance Dossier Nov 2024 BB.T-D1.1.6 Second upgrading of the ACB MPH for TBM FDR Jun 2025 BB.T-D1.2.5.1 Second upgrading of the BN MPH for TBM FDR Jun 2025 BB.T-D1.2.5.2 Grade selection and procurement specifications of BN for TBM Jun 2025 BB.T-D2.1.4 Second upgrading of PbLi MPH for TBM FDR Jun 2025 BB.T-D4.1.1 Report on construction and commissioning of the HCPB TER Facility Jun 2026 BB.T-D4.2.1 Report on construction and commissioning of the WCLL TER Facility Jun 2026 BB.T-D1.3.2.1 Final report of ACB-ABN irradiation. Nov 2026 BB.T-D1.1.3.1 Final report on ACB pebble for DEMO (Development, Qualification, Road Map Supply) Jun 2027 BB.T-D1.2.3.1 Production specification of Beryllide rods as neutron multiplier Jun 2027 BB.T-D4.2.2 Report on Integral Test of WCLL TER Technologies for CDR Jun 2027 BB-S-D.G3.DEF G3 Definition Dossier Nov 2027 BB-S-D.G3.JUS G3 Justification Dossier Nov 2027 BB-S-D.G3.PER G3 Project Performance Dossier Nov 2027
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Grant Milestones ID Milestone Date BB.M-MKOM Kick off Meeting of BB Package Jan 2021 BB.T-M1.4.3 Performances of HCPB TBM TES tested Dec 2021 BB.T-M2.2.1 GLC performances for TBM tested Dec 2021 BB.T-M1.2.1 Production of Beryllide roads achieved Dec 2022 BB.T-M1.3.1 Start of ACB and ABN Irradiation Dec 2022 BB.T-M2.4.3 Performances of coating technology for TBM application tested out-of pile Dec 2022 BB.T-M1.3.2 ACB-ABN irradiation: end of irradiation Dec 2023 BB.T-M2.2.2 Selection of T extraction technology from PbLi Dec 2023 BB.T-M2.3.1 Definition of a water chemistry for the WCLL achieved Dec 2023 BB.T-M2.4.1 Selection of reference steel-PbLi coating technologies in BB and TER Dec 2023 BB.T-M1.2.2 Selection of Beryllide grade for DEMO Hex-rods Jul 2024 BB.T-M3.1.2 Preliminary selection of specific manufacturing technologies and assembling routes for Jul 2024 HCPB and WCLL Concepts BB.S-MG2 Gate G2 Dec 2024 BB.T-M1.1.6 ACB MPH for TBM FDR issued Jul 2025 BB.T-M1.2.5 BN Specification for the TBM procurement reached Jul 2025 BB.T-M2.1.4 PbLi MPH for TBM FDR issued Jul 2025 BB.T-M4.1.1 Construction of HCPB TER facility achieved Jul 2026 BB.T-M4.2.1 Construction of WCLL TER facility achieved Jul 2026 BB.T-M1.3.2 Irradiation properties for ACB and ABN achieved Dec 2026 BB.T-M1.1.3 Optimisation of ACB production concluded Jul 2027 BB.T-M1.1.3 Production specifications and properties of Neutron multipler issued Jul 2027 BB.T-M3.1.3 Definition of manufacturing technologies and assembling routes for driver and test Jul 2027 blankets in DEMO BB.T-M4.2.2 Integral Test of WCLL TER Technologies for CDR achieved Jul 2027 BB.S-MG3 Gate G3 2027
International Collaboration Country Description of Collaboration China The objectives of the collaboration are: Perform collaborative design of water cooling for different blanket concepts. Perform a benchmarking of tritium permeation barriers based on different technologies. Achieve neutron irradiation of functional materials. Additional objectives are under preparation and will be included as soon as agreement with Chinese counterparts will be achieved. The topic presently under discussion is: Tritium balance in the Breeding Blanket: modelling and simulation Extra budget in WPBB for the FP9 has not be included in this document (this programme is in negotiation); missions will be financed through a separate extra budget. Japan The EU-JA collaboration is inserted in the framework of Broader Approach Activities. The WPBB is involved in the following activities: R&D on the Neutron Irradiation experiments of Breeding Functional Materials in BA Phase II R&D on Development of Material Corrosion Database in BA Phase II DEMO design Extra budget in WPBB is not foreseen; missions will be financed through a separate extra budget. Russia The collaboration proposed with Russia foreseen: 1) use of fission reactors for irradiation of functional materials (see also JA-IC). 2) Qualification of mock-up of WCLL in the new facility under construction (LiPb loop with super- conducting magnet up to 5,5 T) at Efremov Institute. The objective of the collaboration is to conduct MHD and heat transfer tests on EU WCLL mock-up to establish pressure drop and temperature distribution. At the present only the irradiation programme has a budget considered in the present WPBB budget; missions will be financed through a separate extra budget.
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Industry Name Description IND-1 Industrial service in support of the BB and TER System design (HCPB and WCLL) IND-2 Industrial service in support of the modelling and assessment of TH experiments for Helium correlation in TBM IND-3 Industrial service in support of the modelling and assessment of TH experiments for PbLi flow in TBM IND-4 Industrial service in support of the modelling and assessment of Tritium transport in TBM and DEMO IND-5 Industrial service for activities related to the procurement of CB for the first TBM IND-6 Industrial service for activities related to the optimization of the Fabrication process of CB to set-up a reliable production route IND-7 Industrial service for activities related to the procurement of BN for the first TBM IND-8 Industrial service for the Development of Beryllides rods as ABN IND-9 Service in fission reactor during the irradiation time IND-10 Industrial service in support of the T test for HCPB TER equipments IND-11 Industrial service for activities related to the PbLi procurement for TBM IND-12 Industrial service for the T test for WCLL TER equipment IND-13 Industrial service for the development of a water cooling chemical control for fusion reactors IND-14 Industrial service for upscaling to industrial level of coating deposition on large surfaces IND-15 Industrial service for manufacturing technologies of BB systems IND-16 Industrial service for manufacturing technologies of FW W protection IND-17 Industrial service for manufacturing and maintenance of HCPB TER facility. IND-18 Industrial service for manufacturing and maintenance of WCLL TER facility. IND-19 Industrial service for construction of infrastructures and storage facility Note: the generic name IND-xx has been used because, at the moment, considering that the call has not been launched yet, the name of the industries cannot be identified for the FP9 programme.
Use of Facilities Facility Name Status Scope of Use Year (New/Upgrade/ Commissioned) HELOKA (KIT) Upgrade TBM scale Helium loop (Loop-1) and Breeding zone (Loop- 2021 2) facility HELOKA-1 (Operation) Execution of tests on HCPB-TBM PMU 2022-2023 HELOKA-1 (Operation) PMU reproducing HCPB manifold distribution test 2024-2025 HELOKA-1 (Operation) PMU reproducing HCPB FW test 2026-2027 HELOKA-2 (Operation) PMU reproducing HCPB Breeding Zone test 2022-2024 WL (tbd) New TBM scale Water loop facility 2021-2023 WL (Operation) PMU reproducing WCLL manifold distribution test 2024-2025 WL (Operation) PMU reproducing WCLL FW test 2026-2027 WBZ (tbd) New WCLL Breeding zone facility 2021-2023 WBZ (Operation) PMU reproducing WCLL Breeding Zone test 2024-2026 HCPB TER-LOOP (tbd) New HCPB tritium extraction loop integrated facility 2024-2026 HCPB TER-LOOP (tbd) (Operation) First Operation period 2027 WCLL TER-LOOP (tbd) New WCLL tritium extraction loop integrated facility 2022-2024 WCLL TER-LOOP (tbd) (Operation) First Operation period 2025-2027 KALOS-UP (KIT) New Ceramic production for TBM procurement and 2021-2024 investigation to industrialization scale for DEMOI KALOS-UP (KIT) (Operation) Operation (pebble production) 2024-2026 MELILO (IPP.CR) Commissioned MELILO (IPP.CR) (Operation) Test of TBM sensor in LiPb 2021-2022 SUSEN (IPP.CR) Upgrade For TBM Programme: AEU (equipment in port cell) test 2021 facility SUSEN (IPP.CR) (Operation) AEU test execution 2022-2023 TLK(KIT) Commissioned Test with Tritium. TLK (KIT) (Operation) Test execution on tritium concentration sensors in He and 2021-2022 data elaboration TLK(KIT) (Operation) Test execution in TLK on getter beds and data elaboration 2021-2022 Page 61 of 143
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HE-FUS3 (ENEA) Commissioned Helium loop for component testing HE-FUS3 (ENEA) (Operation) Tests execution on sensors and data elaboration 2021-2022 IELLO (ENEA) Commissioned PbLi loop for component testing IELLO (ENEA) (Operation) Execution of tests on WCLL-TBM PMU 2021-2022 DIADEMO (CEA) Commissioned Qualification of fabrication mock-ups in PbLi for TBM and 2021-2024 DEMO. MAPLE (KIT) Commissioned MHD tests in PbLi at high temperature 2022-2026 (for that time) MEKKA (KIT) Commissioned MHD tests in NaK at low temperature 2021-2026 LIFUS5/Mod3 (ENEA) Commissioned Safety demonstration of component under PbLi/water 2021-2026 interaction LIFUS II (ENEA) Commissioned Development and characterisation of antipermeation 2025-2027 coating for the TBM of ITER TRIEX (ENEA) Commissioned Test of tritium extraction technologies from PbLi 2021-2023 CiCLo (CIEMAT) Commissioned Study and characterization of corrosion products under 2021-2024 normal reactor condition, correlated with the impurity level of the PbLi. CLIPPER (CIEMAT) Commissioned Test hydrogen/deuterium extraction from PbLi with PAV. 2021-2024 Test different materials to be used as membrane of the PAV LVR-15 (IPP.CR) Commissioned Experimental fission reactor (light water pool type). 2021-2023 Neutron irradition of protective coatings with and without presence of PbLi, tritium permeation studies. RVS-3 (IPP.CR) Commissioned Reactor water loop; corrosion tests in water of structural 2021-2023 materials and WCLL components mock-ups at PWR conditions under neutron irradiation. HELCZA (IPP.CR) Commissioned HHF tests of FW mock-ups and/or BB module mock-ups 2021-2024 HIVE (CCFE) Commissioned Rapid cyclic (fatigue) testing of components, high number 2021-2024 of cycles (full life testing) with possibility of test to failure. FW with W coating testing. Note: For some facilities a programme (under operation) has been already identified because unique or because a precise request from F4E. The other are available, but a precise programme has not be identified (it will depend on which EFL are selected in the call).
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Main Risks Risk Description Risk Impact Mitigation Strategy Higher costs for the project The activities will not be performed Inform PB and PMU about any possible increase than expected (in particular, resulting in incomplete project work of the budget and ask for a re-definition of the hardware costs) work No construction, upgrade, Delay of the provision of data for Distribution of experimental campaigns on all commissioning or shut codes validation, testing mockup, suitable and available facilities worldwide down of facilities or neutron irradiation of functional irradiation facility materials lack of experimental data Launch experimental campaign as soon as for the validation of the design promising facility are identified, constructed, upgraded, commissioned. Design cannot be realized Search for alternative options create a Evaluations of new needs in terms of design with the current concept delay in the BB and auxiliary systems development, experiments and facilities. variants identified design Development of new work plan transferring the budget allocated for previous activities to the new ones Lack of interaction with Lack of coordination and Regular WPBB review meeting will be held to design teams communication between design ensure that the contents of deliverables fulfil teams in different associations technical specifications. Technical specifications of project deliverables are not fulfilled, delays in Point of contacts with others WPs (WPMAT, project milestones or impossibility to WPRM, etc.) identified. PLs and Lead Engineers verify all requirements systematically invited to WPBB reviews. Loss of competencies The activities will not be performed Discuss with the laboratories involved in the required for the running of resulting in incomplete project work project the way to identify missing the project activities competencies.
Inform the Project Board about the situation. The PB shall find the missing competencies in other laboratories Political instability in EU The project is curtailed or totally No mitigation action. Risk accepted. policies relating to abandoned resulting in loss of already EUROFUSION expended time, cost and effort Lack of interest by Resources are unavailable for Identification of other partners participating organizations performing the activities resulting in in WPBB programme. abandoned work
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11 Plant Electrical Systems (WPPES) Objectives The scope of the work package Plant Electrical Systems (WPPES) is to design all systems aimed at providing the required power to plant electrical loads and deliver the net power produced by the generator to the grid. To reach this scope, several specific objectives are identified: Develop a concept design of the key subsystems of the DEMO Plant Electrical System, including: o Definition of a reference PES concept design based on mature technologies9; o Identification of issues preventing the confirmation of known technologies when scaled to the DEMO size; o Identification of areas where improvements/ innovation are required; o Support the concept design of the balance of plant, in particular, the generator design. Implement an R&D plan and modelling activities: o To explore the feasibility and convenience of adopting alternative technologies already used in industrial applications, but at much lower power ratings; o To increase the knowledge on electrical energy storage to identify the most suitable technologies that maximise energy exchange within the plant, without requiring high power peaks to the generator or the grid; o To develop, together with industry, innovative design solutions such as a Magnetic Energy Storage and Transfer System (MEST) and explore their feasibility in DEMO, e.g. for the supply of the Central Solenoid and Poloidal Field coils. Identify and select the most suitable technologies for the different PES subsystems and proceed with the whole DEMO PES concept design.
9 This will be done according to an ITER-like approach where applicable, and in accordance to the design of the PES of Nuclear Power Plants (NPP) for the remaining parts. Page 64 of 143
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Description of work
WPPES R&D G2 G3
2021 2022 2023 2024 2025 2026 2027 generator
Turbine Input from BoP tech
Generator tech. & configuration development in line with PHTS & BoP variants Generator testing activities .
Goal: Selection of NPP technology or development of alternatives Goal: Integrated design with steam turbine
Electrical Electrical
storage energy Exploration of elec. storage systems Goal: Identification of suitable options Input to all tech. R&D below
Exploration of available PS topologies based on VSC with AFE & SuperCap Electrical energy storage Electrical energy
Goal: Feasibility & application for PF & CS coils PS power supplypower MEST small scale prototype dev. & MEST: full power study &
discharge techdischarge test prototype Feasibility of MEST application for CS & PF coils Goal: Proof of principle Goal: Feasibility & app. for PF Feasibility outcome based on MEST results
( MMC with ultra-cap prototyping & test PS Goal: Relevance for DEMO PF coils PS
) ) Technology selection for SC coils supply and fast discharge & &
. Technologies for dc current interruption Testing of selected PS & FD schemes fast fast
, , Goal: RAMI improvements for FDU & coil backup protection Goal: Validation of selected scheme coil Integration studies PS scheme select.
Goal: identify issues Goal: Confirmation supply HCD HCD power HCD mix input MMC technology for HV PS of HPS systems Goal: Feasibility & applicability Selection of PS technologies CD development &
suitable for DEMO HCD mix consolidation (
PS Exploration of solid state RF generators & further development Goal: Validation of selected tech. Goal: Confirmation of
) Goal: Feasibility at DEMO power levels & suitability for HPS systems for DEMO solution
WPPES Design G2 G3 2021 2022 2023 2024 2025 2026 2027
All Collection / elaboration / updates of ELL, requirements / interfaces, power profiles
Goal: Req compliance, effective integration
systems PES sub Prelim. CD according to approaches adopted in ITER/NPP Applicability of ITER/NPP
- Goal: Applicability when scaled to DEMO/identify issues technologies for DEMO HCD HCD
PS Intermediate PS Development of CD for HCD PS component design Goal: Compliance with selected HCD mix
for HCD
state state elec
network Steady Steady CD development Goal: Compliance with req. and SIC/IP load needs
. . Preliminary SSEN design
switchyard power power dist
HV CD development Intermediate HVS & Goal: Compliance with req. of internal loads & ext. power dist. design
power transmission grid
. /
Performance comparison,
Coil Coil PS system
supply Prelim. CD according to alternative solutions identified tech. selection and CD dev. Goal: Verification of suitability for DEMO Goal: design soundness Fault analyses in PF/TF coil circuits at system level Preliminary integrated SC
Goal: Max. requirements for currents/voltages in fault scenario coil PS component design
Generator Turbine Development of CD turbine generator CD generator development & validation Goal: Compliance with BoP variants Goal: Compliance with BoP config. & req
Preliminary TG design
systems
All All PES sub PES Conceptual Design finalization Final
- Goal: Compliance with final req. PES CD
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Grant Deliverables ID Deliverable Date PES.P.D01 PEP10 2021 PES.T.CPS-D001 Report on development and tests of a small scale prototype of the MEST 2022 PES.T.CPS-D003 Report on the applicability/non-applicability of technologies adopted in ITER or NPP when 2023 scaled to DEMO size PES.S.CPS-D001 Preliminary design of the TG in line with the BB PHTS&PCS variants 2023 PES.S.CPS-D003 Preliminary design of the Steady State Network 2024 PES.T.CPS-D005 Report on studies of MEST to explore applicability at full power for the supply of CS and PF 2024 coils PES.T.CPS-D007 Report on comparative analysis among the alternative technologies for SC coils PS and 2025 fast discharge PES.S.CPS-D004 Preliminary integrated design of the SC coils PS components 2025 PES.S.CPS-D005 Preliminary conceptual design of PS components for the H&CD systems 2026 PES.S.CPS-D006 Conceptual design of HVS and Power Distribution system 2026 WBS- S.CPS-D09 Overall PES Conceptual Design 2027
Grant Milestones ID Milestone Date PES.T-M01 First outcome on the feasibility of the MEST based on tests results 2022 PES.T-M02 Applicability/non-applicability of technologies adopted in ITER or NPP when scaled to DEMO size 2023 PES.S-M01 Completion of the preliminary design of the TG 2023 PES.S-M02 Completion of the preliminary design of the Steady State Network 2024 PES.T-M04 Feasibility assessment of the application of the MEST for the supply of CS and PF coils 2024 PES.T-M06 Selection of technologies for SC coils supply and fast discharge 2025 PES.S-M03 Completion of the preliminary integrated design of the SC coils PS components 2025 PES.S-M04 Completion of the intermediate design of the PS components for H&CD systems 2026 PES.S-M05 Completion of the conceptual design of HVS and Power Distribution 2026 PES.S-M07 Completion of the PES conceptual design 2027
International Collaboration Country Description of Collaboration Japan Possible collaboration on the HV technology at MV level for the NBI AG supply that has been developed by Hitachi and in our knowledge is not available in EU China TBC Possible collaboration on the technology used in the HVDC transmission for NBI AGPS in the cases EU companies (ABB, Siemens) are not interested to be involved China TBC Possible collaboration on tests of high power prototype of the MEST or other promising topologies or insulation tests on SC coils in the case a sufficiently large test facility will be not available in Europe
Industry Name Description * Prototypes development of advanced power converters * Involvement in the PES conceptual design * call for tender to be done
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Use of Facilities Facility Name Status (New/Upgrade/Commissioned) Scope of Use Year RFX Thy_conv Commissioned Tests on advanced power converter TBD prototypes
Main Risks Risk Description Risk Impact Mitigation Strategy Lack of interest from laboratories in PES CD not completed on time To spread the culture in the field in the contributing to the PES Conceptual fusion community and to grow young Design (CD) development researchers Lack of interest from companies in CD feasibility not confirmed by To explore possible spin-offs of the R&D being involved in the PES CD the industry, limited design relevant for other applications in the development soundness market Unnecessary overrating of the electrical CD not optimized; higher cost and Joint work to try optimizing plasma power system and power supply size not justified scenario and power needs of the load systems The feasibility studies will show that the no viability of this design To start exploring soon other alternatives MEST is not applicable / convenient for alternative for the CPS the SC coil supply Possibility of instability phenomena in DEMO operation disturbed or Development of an overall model of the the electrical network during fast even generation of faults plant to analyze in advance this risk and transient investigate on possible countermeasures Impossibility to qualify versus tokamak Licensing issues Move the components in area with environmental conditions (EC) milder EC or outside the tokamak building
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12 Divertor (WPDIV)
Objectives The work package Divertor (WPDIV) integrates the design and technology R&D of power exhaust solutions for the divertor regions and limiters of the existing devices W7-X and JT-60SA, as well as the future devices I-DTT and DEMO. The objectives of WPDIV for FP9 are as follows: Develop and demonstrate feasibility of actively cooled W divertor PFCs for W7-X within the technical boundary conditions of the existing device, by full scale prototype manufacturing and high-heat-flux testing Develop and demonstrate feasibility of actively cooled W divertor PFCs for JT-60SA within the technical boundary conditions of the existing device, by full scale prototype manufacturing and high-heat-flux testing Support the design, qualification R&D, fabrication, assembly and installation of the divertor (PFC+cassette body) and the subsystems which have an interface with the divertor. Provide the concept design of the DEMO divertor and limiter systems. Down select and demonstrate feasibility of technology options for DEMO target PFCs, by medium-scale target mock-up manufacture and high-heat-flux testing. Develop coolant pipe corrosion protection & pipe joining technologies for DEMO HHF PFCs.
Description of work W7X W-Divertor R&D W7-X: W-divertor R&D 2021 2022 2023 2024 2025 2026 2027
DIV.W-M01 DIV.W-M02 DIV.W-M03 DIV.W-M04 Divertor concept development & qualification programs
W-HHF prototype development & fabrication
W-HHF prototype tests
W-HHF fabrication
JT60-SA W-Divertor R&D JT-60A: W-divertor R&D 2021 2022 2023 2024 2025 2026 2027
DIV.J-M01 DIV.J-M02 DIV.J-M04 DIV.J-M05 DIV.J-M03 DIV.J-M06 Divertor concept development & qualification programs
W-PFC prototype development & fabrication
W-PFC prototype tests
Divertor cassette development
W divertor PFC/cassette fabrication (undertaken by F4E)
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I-DTT Divertor and interfacing Systems The workplan for the procurement of the first divertor of the Italian Divertor Test Tokamak (I-DTT) has been defined by taking into account the following financial and technical boundary conditions11,12 Design, qualification R&D, fabrication, assembly and installation and of the system divertor and the subsystems which have an interface with the divertor. These includes: o divertor PFCs and supporting cassette bodies. Their fabrication shall start after milestones PEX.M012 and IDTT.M012, as appropriate, have been reached o Pumping, RH of divertor system, Cooling, Divertor Diagnostics, In-vessel coils + power supplies, CODAC, First Wall, Vacuum Vessel. The Gantt chart describing the sequence of the main activities the is shown below:
11Ad Hoc Working Group to define a strategy for the involvement of EUROfusion in the design and procurement of the divertor of the Italian Divertor Test Tokamak (I-DTT) EUROFUSION GA (20) 29 - 4.5 - Involvement of EUROfusion in DTT (Decision) Issue 1.docx 12 Main milestones: IDTT.M0: IDTT ready for completion at low risk, IDTT.M1:demonstration that remaining fabrication will be completed at low risk, i.e., the following items ready by 2022 (nominal): 6 toroidal field coils (TFC), 6 vacuum vessel (VV) sectors, 3 pairs of poloidal field (PF) coils delivered and accepted, 3 of 6 Central Solenoid (CS) coils factory tested, 6 gyrotrons on site tested. IDTT.M2: demonstration that assembly will be completed at low risk, i.e., start of assembly activities, cryostat base assembled, PF4-PF6 assembled, 2 VV + 3 TFC assembled. IDTT.M3: demonstration that machine can be commissioned successfully, i.e., diagnostics-commissioned. IDTT.M4: demonstration that the financial and human resources are available for project completion. PEX.M0: EUROfusion ready for a decision on an alternative exhaust concept. PEX.M1: Demonstration of an alternative divertor configuration to meet DEMO requirements. PEX.M2: Demonstration of an alternative PFC design to meet DEMO requirements. Page 69 of 143
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IDTT: Procurement of divertor & interfacing subsystems PEX.M0 & IDTT.M0 2021 2022 2023 2024 2025
DIV.D-M01 DIV.D-M03 DIV.D-M06 DIV.D-M07 DIV.D-M09 DIV.D-M02 DIV.D-M04 DIV.D-M08 DIV.D-M10 DIV.D-M05 DIV.D-M11
DIV.D-M12
(
prototype Divertor
PFC Design & analysis R&D and/or qualification & Manufacturing & acceptance testing
Assembly/installation
)
(
prototype
cassette cassette Divertor Design & analysis R&D and/or qualification & Manufacturing & acceptance testing
Assembly/installation )
Design & analysis R&D and/or qualification & system Pump Pump testing
Manufacturing & acceptance
Assembly/installation divertorsyst Handling ofHandling Design & analysis R&D and/or qualification & Remote testing Manufacturing & acceptance
Assembly/installation .
Design & analysis R&D and/or qualification & Cooling system testing
Manufacturing & acceptance
Assembly/installation
diagnostics Design & analysis R&D and/or qualification & Divertor testing Manufacturing & acceptance
Assembly/installation
In
- coils vessel Design & analysis R&D and/or qualification & Manufacturing & acceptance testing
Assembly/installation
In
coil PS - vessel Design & analysis R&D and/or qualification & Manufacturing & acceptance testing
Assembly/installation Codac Design & analysis R&D and/or qualification & Manufacturing & acceptance testing
Assembly/installation First wall Design & analysis R&D and/or qualification & Manufacturing & acceptance testing
Assembly/installation
Vacuum Vacuum vessel Design & analysis R&D and/or qualification & Assembly/installation testing
NB: Input of detailed drawings & preparation of procurement specifications, followed by call for tender period
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DEMO Divertor and Limiters
WPDIV R&D G2 G3 2021 2022 2023 2024 2025 2026 2027
Small-scale advanced target mock-up fabrication & HHF testing Goal: Verification of joining technologies (brazing & HRP) Advanced target Medium-scale test prep. down selection & Validation of verification selected solution Medium-scale composite pipe fabrication & testing Medium-scale advanced target mock-up testing (selected)
Goal: HHF performance verification Target Small-scale radiation-resistant target (Cr) fabrication & HHF testing Verification of n- Validation of Goal: Verification of technology feasibility resistant target tech. solution Test preparation Cr radiation resistant target testing Goal: HHF performance verification
Cu-Au brazed alloy characterisation Alternative alloy characterisation Goal: Trans-mutation imitation Goal: Trans-mutation imitation
Small-scale neutron tomography & diffractometry Neutron tomography & diffractometry Goal: 3D micro-structural imaging & residual stress measurements Goal: 3D imaging & residual stress characterisation
Manufacturing tech. verification Cassette body manufacturing tech. Cassette body mock-up fabrication Back-up option mock-up fabrication (if needed) Goal: Dev. of joining & forming tech. Manufacturing tech. verification Shielding liner & reflector Shielding liner & reflector mock-up Shielding liner & reflector hydraulics testing manufacturing technology fabrication Goal: Cooling performance validation Goal: Dev. of joining & forming tech. Cooling concept verification Validation of solution Cassette Target cooling circuit fabrication Circuit hydraulic tests Target cooling concept optimisation Goal: full-scale demonstration Target fixation concept verification Validation of solution Small-scale target fixation Medium-scale target fixation mock-up fabrication & testing mock-up fabrication & testing
Cassette fixation concept verification Validation of solution Preliminary cassette fixation mock-up fabrication & testing Attachment assembly mock-up fabrication & testing
Joining technology verification Validation of solution Preliminary joining technology dev. Joining technology verification Joining technology demonstration for pipework complex
Armor materials manuf. tech. dev. Armor materials architecture optimisation Limiter Limiter PFCs
Armor materials characterisation & extreme heat flux test Limiter tech. verification Small-scale limiter mock-up fab. & medium heat flux test Medium-scale limiter component mock-up fabrication & test
Corrosion protection tech. verification Supporting tasksSupporting Cooling circuit protection coating dev. Protection process optimisation Large-scale cooling pipe anti-corrosion coating processing
Corrosion-erosion test First phase long-term test Goal: Upgrade water-loop set-up Corrosion-erosion rate assessment Preliminary corrosion-erosion test Second phase long-term corrosion-erosion test
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WPDIV Design G2 G3 2021 2022 2023 2024 2025 2026 2027
HHF target design & analysis HHF target design verification Target
MHF target design & analysis MHF target design verification
Structural design assessment (basic guidelines) Structural design assessment (advanced criteria)
CAD modelling (interim version) CAD modelling (revised version)
Multiphysics analyses for interim version Multiphysics analyses for revised version
Cooling circuit design for interim version Cooling circuit design for revised version Cassette Cassette attachment design for interim version Cassette attachment design for revised version
PFC fixation design for interim version PFC fixation design for revised version
Design definition (interim version) Design definition (revised version)
Load specification (interim version) Load specification (revised version)
System integration design System integration verification Limiter Basic design concept development & verification Full-scale design concept development & verification
System integration design (core system)
Supporting tasks Structural integrity assessment & failure modelling
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Grant Deliverables ID Deliverable Date DIV.W-D01 Interim report on results of the W7-X W-divertor qualification program 2023 DIV.W-D02 Final report on W7-X W-divertor concept development and qualification program 2024 DIV.W-D03 Interim report on the results of the W7-X W-divertor PFC high heat flux testing 2024 DIV.W-D04 Final report on W7-X W-divertor PFC prototype testing 2027 DIV.J-D01 Report on JT-60 SA W-divertor concept 2023 DIV.J-D02 Report on JT-60 SA W-PFC development and fabrication 2024 DIV.J-D03 Report on JT-60 SA W-divertor PFC prototype testing 2025 DIV.J-D04 Report on JT-60 SA divertor cassette development 2025 DIV.D-D01 Specification for I-DTT divertor manufacturing and control feasibility 2021 DIV.D-D02 Report of interim design definition of I-DTT divertor prototype, interfaces and other 2021 divertor system components DIV.D-D03 Detailed drawings and procurement specs for divertor pumps, divertor RH, cooling system, 2021 divertor diagnostics. DIV.D-D05 Detailed drawings and procurement specs for divertor PFCs and Cassette, in-vessel coils 2022 and associated power supplies, CODAC and first wall DIV.D-D06 Report of final design definition of divertor prototype, interfaces and other divertor system 2023 components DIV.D-D07 Final report on full scale divertor mock-up manufacturing 2023 DIV.D-D08 Report of interim demonstration tests to assess RH operations, feasibility of installation 2023 procedures, accuracy/ alignment, interfaces DIV.D-D10 Report of manufacturing and acceptance of the internal coils conductors, associated power 2024 supplies, CODAC and first wall DIV.D-D11 Final report of manufacturing and acceptance of divertor PFCs and cassettes an their 2025 integration DIV.D-D12 Report of manufacturing and acceptance of the remote handling systems 2025 DIV.D-D13 Commissioning reports 2025 DIV.P.01-D01 DIV R&D Plan 2021 DIV.T.01-D04 Report on DEMO divertor shielding liner & reflector manufacturing technology 2022 DIV.T.03-D06 Report on DEMO Limiter armour materials manufacturing technology 2022 DIV.T.02-D09 Report on DEMO divertor - medium scale composite pipe fabrication & test 2023 DIV.T.04-D11 Test results from preliminary flow-assisted corrosion test at an industry facility 2023 DIV.T.02-D12 Report on DEMO divertor - advanced target small-scale mock-up fabrication & HHF testing 2024 DIV.T.01-D17 Report on DEMO divertor - Cassette shielding liner & reflector small-scale mock-up 2024 fabrication DIV.T.03-D22 Report on DEMO limiter PFC small-scale mock-up fabrication & MHF tests 2024 DIV.T.02-D25 Results from DEMO divertor - selected advanced target medium-scale mock-up HHF test 2027 campaign DIV.T.01-D28 Results from DEMO divertor - Cassette shielding liner & reflector hydraulics test campaign 2027 DIV.T.04-D34 Results from second phase long-term flow-assisted corrosion test campaign 2027
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Grant Milestones ID Milestone Date DIV.W-M01 W7-X W-Divertor concept interim design review 2023 DIV.W-M02 W7-X W-Divertor concept complete 2024 DIV.W-M03 W7-X W-Divertor PFC prototype complete 2026 DIV.W-M04 Final report on W7-X W-Divertor PFC prototype tests 2027 DIV.J-M01 JT-60SA W-Divertor concept interim design review 2022 DIV.J-M02 JT-60SA W-Divertor concept complete 2023 DIV.J-M03 JT-60SAW- Divertor PFC and cassette prototype development and fabrication complete 2023 DIV.J-M04 JT-60SAW-Divertor PFC and cassette prototype feasibility design review 2024 DIV.J-M05 JT-60SA W-PFC and cassette prototype development and testing complete 2025 DIV.J-M06 JT-60SA W-Divertor pre-fabrication review 2025 DIV.D-M01 I-DTT-Divertor PFC concept complete 2021 DIV.D-M02 I-DTT-Divertor cassette design complete 2021 DIV.D-M03 I-DTT-Divertor PFC R&D and testing complete 2022 DIV.D-M04 I-DTT-Divertor design review 1 2022 DIV.D-M05 I-DTT-Divertor cassette R&D and testing complete 2022 DIV.D-M06 I-DTT-Divertor cooling system and divertor diagnostics procurement complete 2023 DIV.D-M07 I-DTT-Divertor in vessel-coils &PS, CODAS and first wall procurement complete 2024 DIV.D-M08 I-DTT-Divertor design review 2 2024 DIV.D-M09 I-DTT-Divertor PFC procurement complete 2025 DIV.D-M10 I-DTT-Divertor cassette procurement complete 2025 DIV.D-M11 I-DTT-Divertor PFC assembly complete 2025 DIV.D-M12 I-DTT-Divertor cassette assembly and installation complete 2025 DIV.T-M03 DEMO divertor - Medium-scale composite pipe fabrication technology development 2023 complete DIV.T-M04 DEMO divertor - Flow-assisted corrosion test facility-ready 2023 DIV.T-M08 DEMO divertor - Cassette system manufacturing technology verification 2024 DIV.T-M09 DEMO divertor - Cassette cooling concept verification 2024 DIV.T-M12 DEMO limiter - technology verification 2024 DIV.T-M13 DEMO divertor - Corrosion protection technology verification 2024 DIV.T-M17 DEMO divertor - Medium-scale limiter fabrication complete 2027 DIV.T-M18 DEMO divertor - Selected target solution verification 2027 DIV.T-M19 DEMO divertor - Selected cassette solution verification 2027
International Collaboration Country Description of Collaboration Japan National Institutes for Quantum and Radiological Science and Technology: JT-60 SA Interfaces Korea Seoul National Univ.: Fabrication of advanced tungsten (composite) armor blocks for divertor targets Korea KAERI (HANARO): Neutron diffraction test for measuring residual stress states in target mock-ups Russia Plasma beam facility for extreme heat flux test of limiter
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Industry Collaboration Name Description of Collaboration Luis Renner GmbH Industrial manufacturing of composite components for advanced target technology DITF Denkendorf Tungsten-wire braiding for fabricating wire-reinforced composite cooling pipes for targets OCAS Refining-metallurgy for producing ultra-high-purity chromium Fraunhofer Institute (IGCV) Additive manufacturing of tungsten-based limiter armour with complex architectures Studsvik AB Corrosion-erosion test of cooling pipes with a protection liner coating ATMOSTAT/ALCEN Consultation on steel forming & joining technology for shielding liner and cassette RINA Consulting - Centro Ceramic coating of divertor target support components for electric insulation based on VPS Sviluppo Materiali S.p.A. or PVD technique ISIS Neutron tomography of divertor target mock-ups FRM-2 Neutron diffractometry of divertor target mock-ups
Use of Facilities Facility Status Scope of Use Estimated Year Name (New/Upgrade/ total cost Commissioned) 7 years [k€] GLADIS Commissioned High-heat-flux test of divertor target mock-ups 840 2022-2027 HADES Upgrade High-heat-flux test of divertor target mock-ups 720 2022-2027 Judith II Commissioned High-heat-flux test of divertor target mock-ups 800 2022-2027 Judith III New High-heat-flux test of divertor target mock-ups 400 2023-2027 HIVE New Medium-heat-flux test of limiter mock-ups 100 2021-2026 QSPA Commissioned Extreme-heat-flux test of target & limiter mock-ups 600 2022-2027 Magnum PSI Commissioned Simultaneous high heat and plasma particle flux 800 2022-2027 CEF-1 Commissioned Hydraulics test of divertor target & shielding liner 150 2022-2026 CEF-1 (tbc) Upgrade Corrosion-erosion test of target cooling pipe samples 350 2021-2026 BR-2 Commissioned Irradiation test of extra materials for target 600 2021-2026
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Main Risks Risk Description Risk Impact Mitigation Strategy Available human resources within Europe Delay in one or several subprojects Attract experts from outside EU, too low restructuring of milestones and deliverables within WPDIV to distribute load, education of young scientists/engineers via special programs (i.e. ERG, EEG) Demonstration of mock-up fabrication not Additional costs, delay of W7-X Use synergies arising from successful within the allocated budget transition to W PFCs simultaneous target development (W7-X) for other devices within WPDIV. Demonstration of mock-up fabrication not Additional costs, delay of JT-60 SA Use synergies arising from successful within the allocated budget transition to W PFCs simultaneous target development (JT60-SA) for other devices within WPDIV. Divertor PFC fabrication not successful Additional costs, delay of I-DTT Renegotiate schedule and budget within the allocated schedule / budget (I- divertor operation allocation with EUROfusion and DTT) ENEA HHF test facility (JUDITH 3) for PIEs of Delay in getting the information on Shifted the PIEs to the EDA phase. irradiated target mock-ups is not available the post-irradiation HHF performance Deposit until a facility is available. Post-irradiation HHF performance of No verified HHF technology eligible R&D of 1-2 alternative technology target does not meet the design for the EDA phase. options (particularly for joining) requirements Industry partners unexpectedly reduce Cascade delay in schedule Seek back-up industry partners their commitment from the original bids Demonstration of mock-up fabrication not No verified manufacturing technology Request for resource increase for successful within the allocated budget eligible for the EDA phase. further R&D trials (DEMO) Unavailability of test facilities Delayed or cancelled tasks Seek back-up facilities
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13 Heating & Current Drive (WPHCD) Objectives The objectives include the design and the necessary R&D to allow the implementation of the Heating and Current Drive (HCD) System for DEMO 1. We should say what the objectives are , not what they include. Can we promise a conceptual design or not? Can we say that we concentrate on EC? The system design will have an overarching consideration to reliability, whereas the R&D will address issues related to key specific performances of DEMO (e.g. 2 hours pulses) and environment (remote maintenance, safety, etc.). The main design and R&D objectives are as follows: Design and integration of the Electron Cyclotron Heating system (from power plug to plasma i.e. from gyrotron, through transmission line to launcher and its microwave beam steering mechanism). Critical Technology Elements of the R&D Programme will be based on the baseline proposed by the WP Review Panel. It should be noted that the uncertainty on the plasma scenario and the identification of suitable options to be considered for the conceptual design phase will impact the final selection and R&D programme.
Description of work
WPHCD R&D G2 G3 2021 2022 2023 2024 2025 2026 2027
Coaxial-cavity tech. fundamental verification Coaxial-cavity tech. Industrial design together with Goal: Single freq. at 170, decisions & design supplier 1s pulse length, SDC
Tube test in Design and construction of a frame for testing of industrial Test in FULGOR FULGOR with components in a pre-prototype with existing MIG Gyrotron new MIG Goal: 170/204 Goal: 170/204 Verification of industrial manufacturing technologies of key GHz, <4ms pulse GHz, <4ms pulse components of a pre-prototype New 2-frequency MIG procurement Tube construction & testing for Upgrade/MDC tech. Industrial design together with Major upgrade tube longer pulse ops (170/204 decisions & design supplier construction & testing GHz, 2 MW,< 1s ) Design and construction of the tests environment for testing MDC const. Test of short pulse MDC construction <1s Test of long of industrial capabilities <1ms MDC (FULGOR) pulses (FULGOR) pulse MDC pulses Verification of industrial manufacturing technologies
Brewster window manufacturing (optimize mechanical and optical parameters, Optimization of mechanics and dielectric measurements Design of a window assembly the design with
Broadband window window Broadband industrial supplier Large diamond Brazing setup forlarge diamond disk disk procurement and experiments INCO to optimize INCO for manufacture test window performance of Quartz window Freq. tunable tube components Testing future windows procurement construction Construction and manufacturing of Simulation and design, initial design option review the window assembly
Investigation of fundamental Double disk window possible Major upgrade of the design of a double-disk window as
& & design showstoppers at ASDEX design upgrades possible backup solution critical Matching Optics Units: Broadband design, mechanics tuning possibilities, integrated concepts, integrated power measurement Alternative operating modes and ACI, thermal concepts, beam tunnel: Major upgrade on the design of critical components and Fundamental work on advanced more robust concepts technologies
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WPHCD Design G2 G3 2021 2022 2023 2024 2025 2026 2027
Define/update performance requirements for the ECRH system Update req. for the complete system incl. less-critical systems definition
Goal Goal Define safety classification for the components Define/update requirement tree and load specs. for Study and solve integration issues with DEMO system subsystems and components
Launcher conceptual design, with continuous adaptation to scenarios and Launcher Launcher design Launcher final adaptation to scenarios and requirements requirements Beam tracing with realistic plasma shapes (with imperfections Beam tracing, deposition range and performance evaluation due to blobs, turbulence) Component layout, dimensioning, material verif.
Component and mechanism design, supporting, alignment, cooling requirements
Critical and minor components design and compatibility verif.
System design System Design management, incl. subsystems and System Design setup and management integration
mm-wave loads on components and surrounding (direct and Revision of mm-wave loads on all components, including less critical
stray) Launcher design Launcher
qualification nuclear loads on components and surrounding (neutrons, gamma) mm-wave and nuclear load mitigation Re-assessment of mm-wave and nuclear loads of all (critical and adaptation checks and less-critical) components thermal load analysis on components and preliminary Thermal load and cooling analysis on all components cooling design including less critical integrated mechanical analysis on components and required integrated mechanical analysis on cooling minor components and optimization
Launcher Launcher structural Port plug struct./mech. design, incl. shielding blocks & flanges Structural components material selection and design analysis
design Port plug and shielding blocks and Port plug less-critical components design and analysis, incl. flange cooling design and analysis cooling
Port plug integration with BB, cooling and other interfaces In-vessel diagnostics design and verif
/ mechanical mechanical Mirror fastening, supply system and shielding (RH-compatible)
Detailed procedures for fastening, unfastening of mirrors and ancillaries (RH- compatible tools)
Port sealing, Feedthroughs, WG, Cooling, Gas, diagnostics, design and selection line
Port Waveguide TL components/ (
mutli matching mirrors layout definition
- TL
cell transmission and verification
) )
& & - beam TL TL components/matching mirror design transition to or selection and integration TL/mirror cooling design and TL diagnostic components development and testing Shutters, pumping and vacuum enclosure design and functional verifications Supporting structures and expansion joints/bellows.
Quasi-optical design optimization, layout and mirror shape optimisation
transmission line Multi
Manuf. method selection and process optimization, metrological verif. - beam Beam distortion and transmission losses evaluation, mirror curvature optimisation
Beam alignment and mirror curvature tolerance evaluation ( MB Mirror material and cooling, mechanical design,
support, alignment system ) )
Mock-up mirrors mechanical design, construction, testing, mock-up line evaluation connection
gyrotrons Individual transmission lines and gyrotron layout,
quasi-optical design TL TL Matching mirror optical surface design, supports, material Matching mirror manufacturing method, support components, and cooling. cooling system design Polarizers (multi-frequency) and load design Polarizers and load manufacturing method and specifications
Integrated ECH system available power/task control strategy, Reliability, Flexibility
systems control Microwave power recovery, frequency change and distribution strategy Integrated control system architecture NTM subsystem control strategy (angle or frequency steering or both) with DEMO control system
Integrated control system architecture, integration of different tasks
systems Special
Vacuum vessel, Brewster windows and double-disk development Selected windows final development and test
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The work for DEMO1 in the field of EC will concentrate on the following aspects: The design of the mm-wave transmission and launcher system (from the gyrotron to the plasma). Two concepts are being considered to enable the mm waves to be deposited at the desired location with a narrow spot size: a) steering the beam by mirrors (similar to ITER but with the mirror further retracted and protected from the plasma) at fixed frequency or b) depositing the power at the right location by matching the gyrotron frequency with respect to the local tokamak magnetic field and focusing with a fixed mirror. The design of gyrotrons capable of generating 2 MW power in CW operation. This requires the use of the coaxial gyrotron concept. For option a) (above) a gyrotron operating at two frequencies will be developed. For option b) the gyrotron needs to be “step tunable” and requires a broadband window, such as a Brewster one, a fast sweeping magnet system and a specialized launcher with fixed focusing mirror for mode control. A multi stage depressed collector (MDC) shall also be developed to increase the efficiency of the gyrotron and therefore of the whole EC system. The R&D activities to confirm the key issues and the manufacturing feasibility of the proposed designs for the mm wave transmission and launcher system, the gyrotron and the broadband window. IC and NB activities that were part of WPHCD in FP8 are moved to Prospective Research and Development (PRD) in FP9. In this frame, design and R&D activities will continue, without integration effort. Physics studies will also continue in parallel (outside the scope of WPHCD) to ascertain the importance of direct ion heating in the DEMO scenarios. Depending on the physics need and/or the progress of the activities in PRD, IC and NB may be considered again as part of the heating system for DEMO in the future. The key IC and NB activities under PRD focus on the key issues for these systems: Design of the systems (integration studies done by the IC and NB teams but without support from the central design team of PMU). R&D activities on key issues for the IC and NB systems until 2024. In particular, for NB, the issue of neutralization efficiency via a plasma neutralizer will be addressed as recommended by the External Review Panel. Other topics encompass beam optics through simulation and experiments and Cs management for 2 hours pulses.
Grant Deliverables ID Deliverable Date HCD PEP13 2021 Operation of short pulse 170/204 GHz gyrotron and MDC report 2022 Fabrication of Brewster window large diamond disk report 2022 Pre-conceptual design for EC launcher 2022 Coaxial gyrotron report 2024 Broadband window and advanced operation of gyrotron report 2024 Pre-conceptual design of EC RF system 2024 Conceptual design of EC RF system for Gate 3 review 2027 Report on coaxial gyrotron upgrade with regards to manufacturability before ED phase 2027 Report on a broadband diamond disk Brewster angle window assembly 2027
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Grant Milestones ID Milestone Date Preliminary launcher reference design 2022 Operation of 170/204 GHz, <4 ms, modular-type pre-prototype in FULGOR 2022 First-of-its-kind operation of a 2-stage MDC at short-pulses (< 1 ms) 2022 Operation of 170/204 GHz, long-pulse (< 1 s) pre-prototype in FULGOR 2023 Operation of first-of-kind short-pulse 2-stage MDC in FULGOR 2023 First-of-its-kind large CVD diamond disk procured 2023 Verified launcher and transmission line reference mm-wave design 2023 170/204 GHz operation at longer-pulses in FULGOR 2024 First-of-kind long-pulse collector installed in FULGOR 2024 Fundamental results on frequency step-tunability in FULGOR using short-pulse window 2024 Solution proposals for key technologies/key components necessary for gyrotron designs 2024 Areas identified and physical design done for a major upgrade of coaxial-cavity technology 2025 Industrial collaboration initiated with regards to manufacturability of gyrotron and MDC 2025 Launcher and Transmission Line conceptual mm-wave design, integrated in the DEMO plant design 2026 Construction of major upgrade of 170/204 GHz, long-pulse (< 1 s) pre-prototype in FULGOR 2026 Final design and construction of a major upgrade of long-pulse 2-stage MDC in FULGOR 2026 Large size CVD diamond disk for broadband window assembly procured 2026 Successful 170/204 GHz operation of a major upgrade at longer-pulses in FULGOR 2027 Major upgrade of long-pulse collector installed in FULGOR 2027 Diamond disk brewster angle window assembly completed 2027 Final reports of industrial collaboration with regards to gyrotron, MDC and window 2027
International Collaboration Country Description of Collaboration n/a
Industry Name Description Thales Electron Devices TED Gyrotron manufacture Diamond Material Diamond disk production and brazing technology Various mechanical industry Development of EC transmission lines components (e.g. polarizers), actuator for TBD launcher mirror
Use of Facilities Facility Name Status (New/Upgrade/ Scope of Use Year Commissioned) FULGOR Soon to be Gyrotron and transmission line components Whole FP9 commissioned at KIT test Gyrotron test Commissioned at EPFL Gyrotron and transmission line components Whole FP9 depending stand test on the availability ELISE and Commissioned at MPG NB source and other NB components (e.g. Funding is only Batman upgrade grid). CW Cs management available until 2024 NIO1 Commissioned at RFX NB source and possibly for Plasma Neutralizer Funding is only available until 2024 Plasma New Simulation of plasma properties to simulate a Funding is only Neutralizer plasma neutralizer using the negative ions available until 2024 experiment produced by NB
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Main Risks Risk Description Risk Impact Mitigation Strategy The programme does not Should ion direct The WPHCD shall maintain a close relation with Physics to follow include integration (for the heating be required, the requirements and then to re-equilibrate the resources if whole FP9) and R&D (after the integration of IC necessary. 2024) for IC and NB. This will and NBI will not be RoX from the ITER programme of IC and NB. For NB, albeit it was not allow these systems to ready for the Gate 2. decided that NBTF Support Activity will not be managed by reach the appropriate level WPHCD, it was agreed the WPHCD PL shall act as Scientific of integration and their Responsible for NBTF Support Activity within EUROfusion, insuring Readiness Level. the coordination with the NB PRD activities.
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14 Tritium, Fuelling & Vacuum (WPTFV) Objectives The goal of the work package Tritium, Fuelling and Vacuum (TFV) is to deliver a conceptual design of all fuel cycle systems of DEMO.. The design will be demonstrated to be technically feasible, technology choices to be viable, and architecture to be licensable. The specific objectives are: Develop an integrated architecture of the TFV systems that is derived from the particle exhaust capability of each possible divertor solution for a given plasma scenario. Demonstrate that tritium is safely contained, inventory reduced and release rates are minimized to as low as reasonably achievable (ALARA). Verify all technologies up to the same technical readiness level (TRL 3 to 4), in particular for the new technologies in DEMO TFV systems that cannot be extrapolated from other machines. Assist the whole DEMO project in design aspects related to tritium and vacuum. [THIS WAS UNCLEAR TO ME…. IT MAY STILL BE…] At gate G2, TFV will support the down-selection expected for related work packages and decide on the final technology choice of the fuel separation in the Direct Internal Recycling loop.
Description of work The TFV work plan will be organised along a number of lines of technology maturation R&D (demonstrating prototypes for all novel technology elements) and design (considering manufacturability, RAMI and viability aspects), in particular for the novel concept of fuel-cycle architecture with three loops that was established in FP8. The Direct Internal Recycling loop (DIR) is the main means to reduce the overall tritium inventory. It contains first-of-its-kind technologies, namely the metal foil pump to separate pure unburnt fuel directly from the exhaust gas together with continuous vacuum pumps (vapour diffusion and liquid ring) based on mercury as operating fluid to make it tritium compatible. The viability of the chosen design will be demonstrated in a dedicated new facility, DIPAK (Direct Internal Recycling Platform Karlsruhe), which will stage-wise integrate the full pump train in DEMO relevant prototypical scale. Pellet injection on DEMO will have to perform at unprecedented requirements in terms of pulse length, frequency and handling capability of a DT gas mixture. To advance current technology, a distributed facility (the EU pellet injector engineering test bed) will be set up. There, the cryogenic extruder will be designed for DT and operated with tritium-free hydrogen gas. The accelerator will be scaled from ongoing design efforts for JT-60SA, and the guiding tube system will be experimentally characterized. The inner tritium plant loop includes a novel technology for protium removal and isotope rebalancing, based on a refined quasi-continuous temperature (or pressure) swing absorption process, which will be further validated, in particular in view of gate G2. The outer loop takes up the tritium as received from the blanket tritium extraction system and includes the tritium recovery of the blanket coolant. Only after gate G2 in 2024, the design of this loop can be tailored to the finally chosen blanket concept. The outer loop technologies, which are challenging due to their potentially very large size, will be delineated from reverse engineering efforts using designs employed at ITER, CANDU and/or other tritium facilities worldwide. To advance the existing architecture of the fuel cycle, a predictive simulator is being developed on the ASPEN Custom Modeller platform. This tool – started in pre-CDA - will be expanded to include physics based descriptions of all system blocks, and to implement an embedded dynamic controller that allows one to mimic operation of the different loops in response of oscillations. The aim here is to Page 82 of 143
Version 6 May 2020 demonstrate the robust controllability of the fuel cycle under all operational phases. The simulator will further be utilized to develop a viable strategy to monitor and control tritium and to convince the regulator that tritium accountancy and non-proliferation aspects are no issue. The design activities encompass the full engineering treatment as known from a chemical plant. This includes the sizing of the systems using an industrially established Plant Design Management System software, developed in collaboration with a partner from nuclear industry []AGAIN, I’M NOT SURE WHAT THE MEANING WAS….]. One of the major outcomes of the design works to be presented at the G3 gate will be a fully documented design compliance and safety compliance matrix, which is mandatory to prepare any future licensing activity.
WPTFV R&D G2 G3 2021 2022 2023 2024 2025 2026 2027
DIPAK facility commissioned DIPAK – Facility setup Goal: Provision of experiment platform
DIPAK – LDP code development validation DIPAK – LDP DIPAK – LDP Goal: Predictive tool to design the DEMO pumps DEMO scale manuf. integration & operation Goal: Goal: Fabrication & DIPAK – LDP manufacture & operate test Manufacturability perf. qualification Goal: Perf. quant. & parametric database DIPAK – MFP integration & DIPAK – MFP DEMO scaling DIPAK – MFP manuf. & commission operation Goal: Integration of sub-syst. Goal: Perf. qualification Goal: Full understanding of Opimization work operation limits DIR loop demonstrated DIPAK – LRP DIPAK – LRP integration & DIPAK – Facility running
DIR DEMO scaling DIPAK – LRP manufacturing of full-size unit operation Goal: Validation & Goal: Application Goal: Qualification for all operational conditions Goal: Perf. characterisation maturation of novel code set
Matter Injection – pellet injection extruder design Goal: Workflow elaboration with known input data and small support experiments
Matter Injection – JT-60SA accelerator adaptation Goal: Compatibility with DEMO req. (DT mix & T-compat.)
Matter Injection – Guiding tube characterisation Goal: Re-confirmation of delivery characteristics & DEMO pellet magnitude of transfer losses injector prepared Matter Injection – Set-up of pellet injection test bed Matter Injection – Pellet injector integration & operation Goal: Provision of test space for readiness build Goal: Performance validation
GDCM – mass balances & dynamics of buffers & mixers Goal: Quantification of dynamic control requirements
Inner Loop Inner GDCM – Integration of pure D2 supply of NBI Goal: NBI integration based on G1 data & performance parameters
IR/PR – PSA experiments continued Goal: Understand PSA operation parameters, identification of materials IR/PR tech. down selection IR/PR – TSA experiments continued (HESTIA) TSA v PSA experiments Goal: Understand TSA operation parameters, Goal: Down selection prep identification of materials
T-plant – Water detritiation by distillation Goal: Analyse to prep. decision T-plant – Invest in H3AT for TFV T-plant – Exploit H3AT for TFV Goal: Prepare T plant processes Goal: Demonstrate tritium plant processes under tritium T-plant – Water detritiation by
CECE Outer Loop Goal: Analyse to prep. decision Trace tritium tech. T-plant – Coolant purification down selection unit integration Goal: Analyse to prep. decision
Experimental development of tritium instrumentation Goal: Real-time & online measurement capability charact.
Technology implementation of fuel cycle simulator Goal: Optimisation of fuel cycle dynamics under varied loads
NB: Indicates input from PSA PRD
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WPTFV Design G2 G3 2021 2022 2023 2024 2025 2026 2027
Simulation Fuel cycle simulator runs Fuel cycle simulator enhancement Goal: Include energy & dynamic control Accountancy concept agreement with safety, regulator, non- proliferation authority
T monitoring & control – Instrument T monitoring & control – Instrument development development implementation Goal: Develop concept Goal: Validate reliable concept
Fuel Cycle – Baseline vacuum system engineering Goal: CAD, PFD, lay-out, concept design, safety, RAMI
Fuel Cycle – Baseline tritium system engineering Integration Goal: CAD, PFD, lay-out, concept design, safety, RAMI Synthesized concept Fuel Cycle – Baseline matter injection system engineering design for fuel cycle Goal: CAD, PFD, lay-out, concept design, safety, RAMI
Fuel Cycle – TFV input to BB, PMI-phys, HCD, DIV for G2 Fuel Cycle – Implementation of G2 output from other WPs Goal: Keep flexibility via information packages to other WPs Goal: Integrate & refine to final solution
Lifecycle analysis Assessment of waste streams Goal: Identify waste streams Goal: Waste handling procedures
Identify safety cases Rigorous safety analysis Integration towards complete req. & safety compliance matrix Goal: PIE analysis & HAZOP Goal: Safety event system answers Goal: Elaborate plant design documentation
Grant Deliverables ID R&D Deliverables Date Complete project plan and strategy with identified project parties 12/2021 DEMO Metal Foil Pump design approval documents 06/2022 Documentation of down-selection of trace tritium technology 12/2022 Documentation to demonstrate inter-loop dynamic control with the fuel cycle simulator 06/2023 Description of tritium monitoring & control concept as agreed with Authorities 12/2023 TFV conceptual design selection documentatiuon 06/2024 Documentation of down-selection of inner tritium loop technology and pellet injection 12/2024 technology Impact analysis of G2 impact on TFV evolution until G3 06/2025 Final assessment of particle exhaust studies 12/2025 Documentation of DIPAK final stage operation with all systems in DEMO scale operates 06/2026 Summary documentation of tritium experiment results 12/2026 TFV concept design validation documentation 09/2027
Grant Milestones ID Milestones Date Metal foil pump design decided 06/2022 Outer Loop system block technologies decided 12/2022 Control loops demonstrated to work 06/2023 Technology down-selection for inner trium loop 06/2024 Pellet Injector Test bed becomes operational 12/2024 Fuel cycle architecture frozen 12/2025 DIPAK becomes operational 06/2026
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International Collaboration Country Description of Collaboration Russia Development of superpermeable materials for application in the metal foil pump (Bonch-Bruevich St Peters burg State University) – Further collaborations under preparation on testing of fuel cycle technology under tritium (Efremov / Sarov) Japan Implementation of joint work in the modelling of detritiation facilities in the outer tritium plant loop and characterization of online tritium analytics in TPL Tokai, under the DEMO R&D Activity in BA Phase II Task 4 (Tritium Technology) – Use of JT-60SA as demonstration of a DEMO-like pellet injection centrifuge technology USA Joint developments in the area of water detritiation (SRNL) and pellet injection (ORNL)
Industry Name Description SAES Getters, Milano, Italy Application of novel high capacity hydrogen getter materials for fuel cycle applications (pumping, storage, extraction) Hermetic, Gundelfingen, Germany Development of tritium-compatible mercury liquid ring pumps Muegge, Reichelsheim, Germany Adaptation of linear plasma sources for generation of suprathermal particles in the metal foil pump AVS, Lübeck, Germany Expert know-how in mercury processing on industrial scale
Use of Facilities Facility Name Status (New/Upgrade/ Scope of Use Year Commissioned) DIPAK New (will re-use components Development platform for maturation of Fuel Cycle vacuum 2024 of existing THESEUS facility) pump technology on prototypical level Pellet New Demonstrate the achievement of technical pellet injector 2024 Injection performance and gain sufficient performance data to Engineering become able to design such a system for DT operation under Test Facility DEMO requirements (that will only become available if the plasma scenario is decided) H3AT New TFV will not contribute to the build but will exploit the 2025 capabilities to mimic fuel cycle behaviour thus that full components can be tested under tritium at most DEMO relevant conditions MC-TSA Upgrade Demonstrate the applicability of membrane-coupled 2022 temperature swing absorption processes for protium removal and isotope re-balancing in the inner tritium plant loop (fundamental validation, no tritium use). DTT New Use as test bed: Installation and operation of a full scale 2025 metal foil pump
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Main Risks Risk Description Risk Impact Mitigation Strategy Non-availability of tritium experts to TFV Not achieving the Integration of international collaborations in this (due to shut-down of running facilities tritium technology area and new ones being built (such as H3AT) maturation goals not becoming available in time) There are only few know-how holder in Significant know-how Know how management: Set up of a technology pellet technology, mainly loss, not achieving the based facility in this area, to have a basis to engage experimentalists, which may abandon pellet injection with know-how holders and to generate their engagement (senior staff) technology engineering data to allow consolidated modelling maturation plan efforts. Direct Internal Recycling concept does not Tritium inventory is Metal foil pump technical design to be work excessive which is a demonstrated and validated, and performance of showstopper the integrated pump train in relevant scale to be shown and to be in line with scale-up predictions.
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15 Balance of Plant (WPBOP) Objectives The objectives of Work Package Balance of Plant (WPBOP) for the CD Phase are to: Provide a concept design of the Primary Heat Transport System (PHTS) for cooling the breeding blanket, vacuum vessel, divertor and limiters, Intermediate Heat Transport System (IHTS-for the Indirect Coupling option) and Power Conversion System, including a sector equipped by the Alternate Blanket having different coolant from Driver Blanket (briefly called PHTS & PCS). The Driver and Alternate Blankets considered are WCLL and HCPB. Provide a concept design of the Decay Heat Removal System (DHRS) dealing with the removal of the Decay Power after an accident14. Provide a concept design for auxiliaries such as Chemical Volume and Control System (CVCS), Chilled Water System (CHWS), and Component Cooling Water System (CCWS). Perform an R&D plan to address the issues related to manufacturing feasibility and performance verification of He blowers, main He-molten salt Heat Exchangers, H2O-molten salt steam generators, water-water primary SG options, steam turbine rotor and blades.
Description of work R&D plans are established to support feasibility/performance/control assessment and validation of the PHTS&PCS systems and components of DEMO (e.g. He circulators, Water-Water WCLL Steam Generator, main Helium Intermediate Heat eXchanger (IHX15), molten salt-water SG, Steam Turbine (ST) and the whole HCPB BB PHTS+IHTS). Significant support of the industry is envisaged in all the R&D streamlines and especially in case of the “Pulsed Steam Turbine “where Industry will perform an R&D activity to identify a suitable ST (rotor& blades) for validation of the concept design of a PCS directly coupled to PHTS operating at low/very low load operation in dwell (PCS Direct Option with Small/No Energy Storage System). A strong industry support is envisaged in the design activities for the development of the concept design of PHTS&PCS options for two DEMO configurations of: WCLL/HCPB Driver (15 sectors) and WCLL/HCPB Alternate Blanket (1 sectors) focusing on such variants selected at the Gate G1 or moving to the on-going variant developed by the Industry (PCS Direct Coupling at low/very low load operation) in case of promising results of the related R&D campaign; resources split on the two DEMO configurations will be proportionate to the readiness of different solutions of Driver and Alternate Blanket considered. At G2, the BB Driver will be selected as well as the PHTS&PCS option so that, later on, its concept design will be developed till its validation at G3. Technology assessment of PHTS&PCS for DEMO, also through Industry studiesy, will complement/integrate the work done in R&D campaigns in order to achieve a comprehensive systems/components concepts confirmation and validation. Concept design development of three process and cooling auxiliaries such as CVCS, CHWS and CCWS are envisaged up to G2 with reference to one of the two DEMO configurations with Driver and Alternate BB, considering this work as a basis for next review, after G2, of the systems design regarding to the selected PHTS&PCS for DEMO selected baseline.
14 This system is included for convenience in the PHTS&PCS chain, even if it is an Emergency Cooling Systems. 15 Should HCPB IC variant not be selected at Gate 2, related R&D campaign shall be re-modulated. Page 87 of 143
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WPBoP R&D G2 G3 2021 2022 2023 2024 2025 2026 2027 HCPB & WCLL ST rotor material selection HCPB & WCLL ST rotor material modelisation
HCPB & WCLL ST rotor Pulsed steam turbine ST rotor materials development & testing Further rotor materials dev. & tests new material Goal: Material data collection characterisation ST mock-up design & boundary condition defined End of tests executed on ST mock-up Low pressure ST test rig design & build for low & very low load ops Post processing
Goal: Design criteria verification for safe ventilation operations test results (
ST ST design criteria
ST design for definition for ) ventilation ops ventilation ops Low pressure ST redesign concept to optimize low-flow ST new design criteria Goal: hydro/mech. Goal: Tuning of design criteria for low-flow behaviour for ventilation design criteria def.
WCLL Eng. Design of OTSG & HCSG mock up water steam generator Demonstration of OTSG & HCSG low Demonstration of full power
power operation perf. of OTSG & HCSG Demonstration of OTSG : :
water Scaled test facility for full power & MS pulsed-dwell ops. Scaled test facility for low load testing testing Pulse-dwell transient testing
Goal: Performance qualification of SGs options Goal: Performance qualification of Goal: performance qualification - SGs options
IHTS mock-up ext. Experimental campaign on HXs
with ESS manuf. ended & concept demonstrated HCPB Ph1: Design & install a scaled IHTS loop for Ph2: Complete IHTS loop with energy storage IHTS+ESS exp. campaign testing of HXs systems & tests ended, ESS concepts
: : Goal: Qualification of He/MS and H2O/MS HXs Goal: Dynamic behaviour of different ESS concepts demonstrated and selected PHTS
Ph3: Design & install scaled PHTS+IHTS loop & tests IHTS loop mock- + + Goal: Eval. of dynamic behaviour of DEMO-scaled
IHTS up manufactured PHTS + IHTS Ph1+: He Blower assessment End of exp. campaign DEMO He blower Goal: Select/improve He blower design & check feasibility & qualification of concept demonstrated Scaled PHTS+IHTS+ESS with DEMO blower mock-up manuf. HCPB PHTS & IHTS concept design
WPBoP Design G2 G3
2021 2022 2023 2024 2025 2026 2027 PHTS
PHTS & PCS selection for PHTS & PCS concept design for concept design DEMO BB baseline DEMO BB baseline
& & PHTS & PCS options design study PHTS & PCS concept design development PCS Goal: Preliminary concept design development for WCLL/HCPB as driver & Goal: Design of selected option for selected BB config.
WCLL/HCPB as alternative
concept design DEMO aux
systems CVCS, CHWS, CCWS CVCS, CHWS, CCWS concept preliminary design design for DEMO baseline Auxiliary cooling/process systems design study Aux. cooling/process systems concept design for BB
Goal: CVCS, CHWS, CCWS prelim. design Goal: CVCS, CHWS, CCWS concept design
. . Technology maturation First tech. assessment Second tech. assessment – of main components validation of key technologies Technology assessment/selection/verification Tech. validation of main PHTS & PCS components Goal: Manufacture feasibility, architecture & sizing, performance verification of Goal: Design & performance validation main relevant PHTS & PCS components
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Grant Deliverables
ID Deliverable Date GD1 BOP Management Plan 2021 GD2 Outline of PHTS&PCS and Auxiliaries Concept Design for DEMO with Drivers and Alternate Blankets 2022 and Auxiliaries (CVCS, CHWS, CCWS) GD3 First Technology Maturation Report on main relevant PHTS&PCS components (feasibility, control, 2023 concept demonstration) GD4 Preliminary PHTS&PCS Concept Design for DEMO with Drivers and Alternate BB Blankets 2024 GD5 Preliminary Auxiliaries Concept Design for DEMO with Drivers and Alternate Blankets (CVCS, CHWS, 2024 CCWS) GD6 Interim Technology Maturation Report on main relevant PHTS&PCS components (feasibility, control, 2025 concept demonstration) GD7 Interim Report on PHTS&PCS and Aux Design Concept Design for DEMO with selected Driver and BB 2026 Blanket (incl. Syst. Reqs., DDD, CAD models, analysis, RAMI and Cost Reports) GD8 Provisional PHTS&PCS Concept Design for DEMO with selected Driver and alternate BB Blankets (incl. 2027 Syst. Reqs. , DDD CAD models, analysis, RAMI and Cost Reports GD9 Provisional Auxiliaries Concept Design for DEMO with selected Driver and Alternate Blankets (CVCS, 2027 CHWS, CCWS) GD10 Provisional Technology Maturation Report on main relevant PHTS&PCS components (feasibility, 2027 control, concept validation)
Grant Milestones
ID Milestone Date GM1 Initial concept design of PHTS&PCS for DEMO with BB Drivers and BB Alternates and Auxiliaries 2022 available GM2 First Industrial and experimental assessment of PHTS&PCS technology maturity available 2023 GM3 Preliminary Concept Design of DEMO CVCS, CHWS, CCWS available 2024 Gate G2 Selection of PHTS&PCS option for DEMO with Driver and Alternate BB 2024 GM4 Second Industrial and experimental assessment of DEMO PHTS&PCS technology maturity 2025 available Gate G3 Concept design of PHTS&PCS for DEMO with selected BB Driver and Alternate available 2027 GM5 Provisional Concept Design of CVCS, CHWS, CCWS for selected DEMO configuration available 2027 GM6 DEMO PHTS&PCS Technology Maturation assessment report available 2027
International Collaboration Country Description of Collaboration USA Collaboration on molten salt technology especially referring to the Helium – molten salt heat exchanger performance and Molten salt Thermocline tank performance
Industry Name Description t.b.d. Support to the concept design development and validation of DEMO He blower; Support to the R&D campaign for the validation of the HCPB PHTS+IHTS+ESS concept design ANSALDO Support to the development of several BOP process and cooling auxiliary systems. NUCLEARE+ Support to the concept design development of the PHTS&PCS options for DEMO with Driver and FORTUM+ Alternate BB. t.b.d. Support to the technology assessment/selection/verification of the main relevant PHTS&PCS components Support to the R&D campaign on WCLL water-water SGs options validation Concept design development of a DEMO PCS directly coupled to PHTS operating at low/very low load operation in dwell and experimental validation of its “pulsed” steam turbine.
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Use of Facilities Facility Status Scope of Use Year Name (New/Upgrade/ Commissioned) HELOKA Upgrade I Coupling of Heloka cooling loop to a scaled Molten Salt (MS) loop for 2021- qualification and optimization of molten salt HXs (HCPB) 2023 HELOKA Upgrade II Extension of Upgrade I with a scaled MS Energy Storage System (ESS) for 2023- dynamics evaluation and ESS selection (HCPB) 2025 HELOKA Upgrade III Coupling of Upgrade II to Heloka High Pressure (HP) for dynamic 2025- behaviour qualification of a scaled HCPB PHTS+IHTS loop with DEMO 2027 blower CEF Upgrade for Low Qualification of WCLL water-water SGs options (OTSG and HCSG) low 2021- Power Ops. power operation 2023 CEF Upgrade for Full Qualification of WCLL water-water SGs options (OTSG and HCSG) full 2023- Power Ops. power operation 2025 CEF Existing Qualification of WCLL water-water SGs options (OTSG and HCSG) for pulse 2026 -dwell transition ops.
Main Risks Risk Description Risk Impact Mitigation Strategy Large efforts required in case of To not have completed the activity to To prioritize, according to WP interfaces, development of PHTS+PCS for perform a selection of at least one one most promising option among both combination of Driver& PHTS+PCS option for both Driver & possible Driver and Alternative blanket Alternative blanket Alternative Blanket Configurations. and focus the PHTS+PCS concept (WCLL/HCPB) to the same development on it while performing a extent. less detailed investigation on the other. Large efforts required in case of To not have completed the activity to Put more effort and increase of budget development of PHTS+PCS for demonstrate the viability of at least one (probably mainly versus Industry) in case selected Driver& Alternative PHTS+PCS option for the selected DEMO of need to continue to develop more blanket if at G1 it will remain Driver and Alternate Blanket than one PHTS+PCS options. more than one PHTS+PCS configuration at G2 option Difficulty to perform a costly R&D campaign could be limited in scope Try to find a way to provide more funding R&D with the present refunding and then full verification/validation of the to labs involved in R&D rules for HW PHTS+PCS concepts could be impaired. Uncertain reliability of some Uncertain timely delivery of the Ask to the involved labs a realistic labs in performing accepted deliverables declaration of maximum # of tasks that it tasks could effectively develop within an established time window
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16 Diagnostics & Control (WPDC) Objectives The objective of the Work Package Diagnostic & Control (D&C) is to develop a feasible, integrated concept design of the DEMO diagnostics and control system that, with an acceptable confidence level, can be shown to provide reliable plasma control in DEMO. To this purpose, R&D of critical components will be conducted and the concept design and integration of diagnostic systems for plasma control will be developed. Based on these, the lifetime and performance of those diagnostics under DEMO conditions (harsh neutron environment, particle fluxes, electromagnetic forces, etc.) will be quantitatively assessed. Control modules will be developed and control simulations will be performed, taking into account the detailed properties of plasma scenarios and of the machine, in particular realistic diagnostics and actuator properties. The goal is develop, refine and optimize the control system and the DEMO parameters towards achieving reliable control in high performance plasma operation. WPDC also contributes to an iterative improvement and refinement of the DEMO control requirements, with regard to feasibility and optimization.
Description of work
WPDC R&D G2 G3
2021 2022 2023 2024 2025 2026 2027
Magnetic sensors Prototype development & qualification sensors & electronics Goal: Hardware fabrication & definition of irrad. conditions
Prototype development & lab test of detectors for plasma
Detectors Comparative test of detectors for DEMO relevant plasma radiation radiation power Goal: Performance results for DEMO relevant conditions Goal: Hardware and performance results
Prototype development & testing of detectors for neutron/ Testing of detectors with collimators & shielding for neutron/gamma gamma measurements measurements under DEMO relevant conditions Goal: Hardware and performance results Goal: Performance results for DEMO relevant conditions
Demonstration of detachment control based on spectroscopic measurements Goal: Validation of the physics & the measurement technique with respect to reliability under DEMO relevant conditions
Prototype dev. & testing of Rogowski Comparative testing of thermocurrent measurement for detachment control via shunt & Rogowski coil coil for DIV thermocurrent measurement Goal: Validation of the reliability of this measurement technique under DEMO relevant conditions Plasma control Goal: Hardware installed
Development of DIV Halo current Measurement of DIV Halo currents arising from plasma transients measurement Goal: Validation of essential boundary conditions for DIV detachment control Goal: Hardware installed
Hardware development for non- Demonstration of equilibrium control based on non-magnetic measurements magnetic equilibrium control Goal: Validation of alternative control approach as a reliable option Goal: Hardware installed
Prototype development of ECE Demonstration of mode control based on ECE measurements and ECR heating channels Goal: Validation of reliable mode control under relevant conditions Goal: Hardware installed
WPDC Design G2 G3 2021 2022 2023 2024 2025 2026 2027
diagnostics
Plasma Development of diagnostics for plasma control on DEMO: Development of diagnostics for plasma control on DEMO: physics design, physics design, feasibility studies, CAD, performance feasibility studies, CAD, performance analysis, RAMI (phase 1) analysis, RAMI (phase 2)
Development of detailed control functions, modules and strategies for all Development of detailed control functions, modules and
Plasma control plasma phases (phase 1) strategies for all plasma phases (phase 2)
Control simulations for a quantitative analysis and Control simulations for a quantitative analysis and demonstration of the demonstration of the controllability of the DEMO plasma controllability of the DEMO plasma (phase 1) (phase 2)
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In the R&D section of the programme, critical issues will be addressed by prototype development and testing under DEMO relevant conditions. The feasibility and durability of magnetic measurements under DEMO relevant neutron irradiation will be addressed by developing prototype sensors, performing irradiation in a fission reactor, and conducting in-situ and/or post irradiation testing of their performance. As a means of risk mitigation, the feasibility of reliable equilibrium control of a tokamak plasma without magnetic diagnostics will be tested over extended periods, for which reflectometry, ECE, IR interferometry and plasma radiation measurements would play an essential role. Several prototype detectors for plasma radiation and for neutron/gamma measurements will be developed and tested with regard to their long-term stability of signals for DEMO relevant conditions. Concerning the signals used for detachment control, various spectroscopic approaches will explored aiming for reliable control over long periods under DEMO relevant conditions. The feasibility of divertor thermo-current measurements will be further tested and the limitations of the measurements arising from halo currents induced by plasma transients will be investigated. Finally, the quantitative boundary conditions for mode control based on combined ECE/ECCD (spatial accuracy and required heating power) will be determined experimentally. In the design part of the programme, details of the diagnostic layouts, integration and space occupation in the tokamak will be further elaborated and the expected diagnostic performance will be analysed, in order to verify the overall feasibility of the D&C concept. The list of control functions will be amended and further detailed, the physics basis of advanced plasma control will be further developed. The corresponding control strategies will be worked out in detail. Finally, the D&C concept will be verified in detail by refined quantitative control simulations. Wherever needed, design iterations will be initiated to improve the overall performance and reliability of DEMO operation.
Grant Deliverables ID Deliverable Date PEP16 2021 Report on prototype development for a Rogowski coil for divertor thermocurrent measurement 2022 Report on development of divertor Halo current measurement 2022 Report on hardware development for non-magnetic equilibrium control 2022 Report on the technical preparation for NTM control based on ECE/ECCD 2022 Report on prototype development and laboratory testing of magnetic sensors and electronics 2023 Report on the development and laboratory testing of detectors for plasma radiation 2023 Report on Prototype development and laboratory testing of detectors for neutron/gamma 2023 measurements WPDC progress report 2024 WPDC progress report 2025 WPDC progress report 2026 WPDC progress report 2027
Grant Milestones ID Milestone Date DC-T-01 Prototype Rogowski coil completed 2022 DC-T-02 Divertor halo current measurement developed 2022 DC-T-03 Prototype components for non-magnetic equilibrium control completed 2022 DC-T-04 Technical preparation for NTM control based on ECE/ECCD completed 2022 DC-T-05 Prototype magnetic sensors completed 2023 DC-T-06 Prototype neutron/gamma detectors completed 2023 DC-T-07 Prototype detectors for plasma radiation completed 2023
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International Collaboration Country Description of Collaboration US Ongoing discussion on collaboration diagnostics development and testing for DEMO conditions (ref. VC meeting 23+24 March 2020)
Industry Name Description t.b.d. Opto-mechanical design studies on the feasibility of optical measurements on DEMO Cosylab System engineering (Cosylab as third party to JSI)
Use of Facilities Facility Name Status Scope of Use Year (New/Upgrade/ Commissioned) AUG and other Testing of prototype components and validation 2022-2027 tokamaks experiments Fission reactor Irradiation testing of magnetic sensors 2022-2027 MST, IDTT, JT-60 Demonstration of reliable equilibrium control based on 2021-2027 DEMO relevant non-magnetic measurements MST, IDTT, JT-60 Demonstration of DEMO relevant mode (NTM) control 2021-2027 MST, IDTT, JT-60 Demonstration of reliable detachment controlbased on 2021-2027 DEMO relevant spectroscopic measurements MST Demonstration of DEMO relevant divertor 2021-2027 thermocurrent and halo current measurements on a tokamak MST Comparative testing of candidate detectors for plasma 2021-2027 radiation power Accelerator, fission Testing of candidate detectors for neutron/gamma 2021-2027 reactor or large measurements, together with collimators and shielding tokamak components, in a DEMO relevant testing environment
Main Risks Risk Description Risk Impact Mitigation Strategy In-vessel magnetic coil based Accurate equilibrium control not Irradiation testing of magnetic sensors measurements strongly affected by possible with magnetic under DEMO relevant fluence; and irradiation effects measurements demonstration of reliable equilibrium control by non-magnetic measurements Feasibility of divertor detachment Stable divertor detachment control Demonstration experiments using DEMO control using DEMO relevant not feasible relevant diagnostics under relevant diagnostics conditions Accuracy of mode (NTM) detection Too high ECCD power needed for Demonstration experiments using DEMO and ECCD beam steering not mode control, or mode (NTM) control relevant measurements and ECCD sufficient may be not reliable enough system under relevant conditions Detectors for radiation power and Burn control (control of Psep (Prad) and Demonstration experiments under for neutron measurements may not of fusion power) may not be accurate DEMO relevant conditions be accurate or durable enough enough or even unfeasible under DEMO conditions
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17 Remote Maintenance (WPRM) Objectives The objectives of the work package Remote Maintenance (WPRM) during the DEMO CD phase are to: Produce integrated conceptual designs of the primary remote handling systems, for; blanket, divertor, limiter, shielding, service connections and pipe work, vacuum pumps, in-cryostat, heating and current drive and diagnostics. Develop the integrated designs of the secondary maintenance systems based on verified technologies including; transport and crane systems, generic maintenance, and contamination control. Prepare a ‘Maintenance Management Plan’. Develop an integrated, consistent maintenance logistics concept to minimize downtime of the DEMO facility Prepare a validated and verified safety case for the maintenance strategies through a continuous (iterative) improvement programme moving from design modelling, bench testing to system level verification at an appropriate physical scale. Develop and initiate a risk mitigation plan for radiation tolerant devices, including studies and testing as appropriate. Design and build the remote maintenance test equipment required to reduce the critical technology risks associated with transportation of the large components (e.g. blankets, limiters divertor); port maintenance; tokamak inspection and maintenance; in-cryostat and ex-cryostat inspection and maintenance. Develop and verify system modelling and simulation tools, and verifythe control systems for: heavy-duty transporters; manipulators; autonomous inspection and maintenance devices. Hold a remote maintenance pre-conceptual design review prior to G2 to ensure alignment of the DEMO plant conceptual design with the approved remote maintenance strategy. Develop a validated and verified ‘Design for Maintenance Manual’ that includes the standard remote handling equipment and interfaces ready for use during the engineering design phase. Support the overall integrated DEMO plant design with the remote handling compatibility assessments. Prepare the equipment design and maintenance process documentation pack to support the conceptual design.
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Description of work
WPRM R&D G2 G3
2021 2022 2023 2024 2025 2026 2027
Service tech
joint Alternative pipe joining and preparation technology development (end-facing, brazing, etc.)
Goal: Verified portfolio of concept pipe connections . Portfolio of pipe connections
Advanced robotics/bilateral development Goal: Research, R&D results, PoP operational demonstration (G2) and concept operation (G3)
Synthetic viewing system development Operation Goal: Real time demonstration Load transfer development
Goal: Load transfer scheme & &
Automated maintenance development control of systemscontrol RH of Goal: R&D results, PoP operational demonstration (G2) and concept operation (G3)
Radiation hardened control development Goal: R&D results
Advanced Realtime trajectory planning Goal: R&D results, operational demonstration
Dynamic virtual transporter development Goal: Verification using TARM, PHMTR and HPTR
Condition monitoring development Goal: Research, R&D results (G2) and operational demonstration (G3) Control system safety case justification
High power density actuation Design for seismic damage mitigation Mechanical system development Goal: Design guidance (rules)
development Goal: Market research and R&D results Dropped loads Goal: Strategies for mitigating against dropped loads
Hardware characterisation library Goal: Hardware library/database
Integrated ground transport system Goal: Proof of concept
Auxiliary technology developmenttechnologyAuxiliary Contamination control methods Goal: Market research and R&D results (G2) Maintenance of LiPb pipes Goal: Market research results Component fixation and earthing system development Goal: Market research and R&D results (G2), concept definitions (G3)
RPV inspection technology development Goal: technology demonstrators of weld visual and volumetric inspection
Logistic simulation development Goal: Realtime demonstration (G2), MPS duration models (G3)
Building (site) to house PHMTR identified Verification Precision high mass test rig (PHMTR) PHM test rig commissioned
infrastructure Goal: Design, build and onsite commissioning
Building (site) to house VPTR identified
& & Vertical port test rig (VPTR)
validation validation VP test rig commissioned Goal: Design, build and onsite commissioning Building (site) to house HPTR identified Horizontal port test rig (HPTR) HP test rig commissioned Goal: Design, build, and onsite commission
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WPRM Design 1/2 G2 G3 2021 2022 2023 2024 2025 2026 2027
Maintenance Management Plan (SRD, Risks, etc.)
Maintenance Management Plan development Maintenance Maintenance engineering Goal: High level principles and concept/outline Goal: High level principles and outline maintenance processes (Draft) systems systems maintenance processes (version 1)
Maintenance Safety Case development Maintenance Safety Case, CDR maintenance strategy Goal: Outline SC, supported by V&V progress report Goal: Version 1 supported by V&V records
Design for Maintenance Manual (R&D report) Design for Maintenance Manual 1st issue Goal: R&D report with verification results Goal: CDR "Design for Maintenance Manual"
Blanket handling design development incl. service connections Concept blanket handling design incl. service connections Goal: Blanket transporter (e.g. end-effector) outline RHE designs Goal: Blanket transporter (e.g. end-effector) concept design Concept blanket handling system PHMTR perf. trials Concept performance evaluation trials (using PHMTR) Goal: Results Goal: Verif. of PoP elements of heavy load transporters to inform BB Phase 1 evaluation results VPTR perf. trials Phase 1 Goal: Upper evaluation results port validation Divertor handling RHE design development incl. service connections Concept performance evaluation trials (using VPTR) Goal: RHE concept design Goal: Verif. of PoP elements of upper port maintenance
First wallmaintenanceFirst Divertor handling PoP trials incl. service connections Goal: Build, onsite commission and verification of the RHE designs
Concept divertor handling system Goal: Divertor cassette transporter (e.g. end-effector)
Upper, lower, and inner/outer midplane limiter handling design development incl. service connections (equatorial port pipe module handling) Goal: Feasibility assessments (G2) and outline MPS (G3)
Equatorial port pipe module handling PoP trials Goal: PoP elements trial results
HPTR perf. trials Phase 1 Goal: Upper port validation evaluation results Performance evaluation trials (using HPTR) Goal: Verif. of PoP elements of horizontal port Tokamak maintenance RHE design development Multi-Purpose Deployer (MPD) design development Goal: PoP elements trial results and outline RHE designs Goal: Pre concept MPD design Reactor Pressure Vessel (RPV) inspection RHE design development Verified RPV inspection Goal: Verified concept RHE designs Rescue and recovery of RHE Goal: Feasibility assessments (G2) and outline RHE design (G3)
Tokamak access ports Port neutron shield handling design development Goal: Feasibility assessments (G2) and outline MPS (G3)
lower Port vessel access design development (shield plug and port closure plate)
Goal: Feasibility assessments (G2) and outline MPS (G3) & &
Integrated port RHE design development Integrated port RHE concept design equatorial Goal: Integrated RHE outline design Goal: Integrated RHE concept design RHE/MPS all port maintenance
operations outline
–
upper Generic port component design development (e.g. diagnostics, pellet, contamination control, cleaning, inspection etc.) Goal: Feasibility assessments (G2) and outline RHE designs (G3)
RHE/MPS maintenance , , operations concept for ports
Tokamak EC and IC launcher maintenance (handling) design development HCD Goal: Feasibility assessments (G2) and outline MPSs (G3)
NB maintenance and handling design development Goal: Feasibility assessments (G2) and outline MPSs (G3)
In-bio-shield (cryostat) maintenance
In-bio-shield (cryostat) maintenance infrastructure concept design maintenance In infrastructure design development
Goal: Integrated RHE design -
bio Goal: PoP element results and RHE designs
Maintenance scheme trial results - shield shield Magnet maintenance and design development Goal: Feasibility assessments (G2), PoP element trial results, and outline MPSs (G3) Vacuum vessel (incl. heat shield) maintenance and design development Goal: PoP element trial results, feasibility assessments (G2)and outline MPSs (G3)
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WPRM Design 2/2 G2 G3 2021 2022 2023 2024 2025 2026 2027
Tokamak building plant roomsplant building Tokamak Pipe chutes and chases (PC&C) maintenance
& & Building layout and RHE integration infrastructure design development
systems systems maintenance Goal: Integrated RHE outline designs Goal: PoP element trial results, outline MPSs Maintenance scheme trial results BoP maintenance design development Goal: Feasibility assessments (G2) and outline MPSs (G3) Port Cell design development Goal: Feasibility assessments (G2) and outline MPS (G3)
Diagnostic design development Goal: Feasibility assessments Key RHE/MPS of tokamak building plant systems maintenance operations
Tokamak building plant systems (ex-bio-shield) generic maintenance
Tokamak building plant systems concept design infrastructure Maintenance Maintenance infrastructure design Goal: Integrated RHE design
support Goal: PoP element trial results and outline RHE designs Maintenance trial results Transport Systems (GBV's, casks, and overhead cranes) Goal: Integration feasibility assessment (G2) and integrated build layout and outline RHE designs (G3) Rescue and recovery systems design development Goal: R&R strategy (G2) and outline equipment designs (G3)
Standardised remote remote handlingStandardised Laser in-bore pipe cutting, welding, NDT RHE/MPS development Goal: Proof of concept for DN80 and DN200
TIG in-bore pipe welding RHE development
equipment Goal: PoP element trial results and outline RHE/MPSs
External pipe welding RHE/MPS development Goal: Market research (G2) and outline RHE/MPSs
Single mechanical pipe connection RHE/MPS development Goal: Market research (G2) and outline RHE/MPSs
Manifold mechanical pipe connection RHE/MPS development Goal: Proof of concept
The framework for the WPRM work plan during the conceptual design phase will be organised so as to achieve a conceptual design for the primary DEMO maintenance systems by 2027. This requires the critical risks to be mitigated to a point where there is a reasonable expectation that the Engineering Design phase can be completed without gross changes to the operating and maintenance strategy and plant layout. Critical risks are those that could have a significant impact on the plant level risks for cost, programme, availability, safety and power plant relevance. The critical technologies required to mitigate such risks need to be demonstrated to be at TRL5 and IRL4 or above. The plant level risks are mitigated by the development of suitable processes to meet the maintenance requirements. These processes require an integrated strategy and level of system design to demonstrate the feasibility of the process. Where the feasibility relies upon technologies, these must be demonstrated to be TRL3 and IRL3 or above, unless it is a critical technology with a significant impact on plant level risks, in which case it must be demonstrated to the higher level of TRL5 and IRL4 or above.
The maintenance processes are mainly driven by the plant architecture, underpinning these is a range of enabling technologies. For example, these technologies need to be understood in terms of risk, maturity and performance in order to inform the down-selection of options. The blanket handling end-effector developed in the pre-conceptual phase is an example of a critical enabling technology, where it is shown that, due to the architecture constraints, the handling of a large blanket segment is currently not feasible and a change in the plant architecture is required. In-Tokamak Maintenance (including access ports) Due to the restricted nature of the access ports and the extreme environmental conditions (radiation, contamination, residual heat and magnetic fields), the integrated processes needed for in-vessel maintenance are of vital importance to the viability of the plant. It is essential that components and
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Version 6 May 2020 the maintenance processes are developed together to provide a unified architectural design. An effective maintenance system requires several consistent foundation elements that typically comprise: component kinematic path planning, location and fixation; safe transportation, dropped load mitigation, rescue and recovery; service connections and contamination control. Tokamak Building Plant Rooms and Systems Maintenance The plant layout will also be driven by the maintenance strategies and the other primary plant systems. It is therefore essential that both the strategies and the primary maintenance process are well developed to ensure the maintainability of the various systems. The ALARA principle will determine to what extent, and under what circumstances, manual maintenance is allowed in this region. However, in the conceptual phase the design must have options to allow remote maintenance across most of the DEMO plant to ensure that it can meet the ALARA principle and also the annual plant integrated dose budget. Additionally, the in-tokamak maintenance processes will be dependent on the integration of overall plant architecture with the maintenance systems if the DEMO plant level risks are to be mitigated. The maintenance within the plant rooms and or system will require an infrastructure that comprises transport systems and routes, generic maintenance infrastructure, contamination control, waste management, active maintenance facility and rescue and recovery system to cover the significant number of wide ranging maintenance processes with heavy loads and complex mechanical and services interfaces. In-bio-shield Maintenance (including in-cryostat) Due to the compact nature of likely access ports and the challenging environmental conditions (radiation, cryogenic coolant, residual magnetic fields, confined space), the integrated maintenance processes needed for the in-cryostat and in-bio shield are of vital importance to the success of the plant. The maintenance in this area will require an infrastructure that comprises transport schemes and routes, generic maintenance infrastructure and rescue and recovery systems to cover the wide range of challenging maintenance processes. Technology Maturation R&D and Verification The technology development activities will focus on establishing the underpinning technologies needed to validate the designs of the novel maintenance systems. These technologies are generally independent from the plant configuration and are not significantly affected by changes to the plant architecture. They cover a wide range, from advanced robotics to clearing LiPb from service pipe work, and include: radiation hardened control and sensing hardware, transport guidance systems, in-situ inspection to meet the regulatory requirements, load transfer, contamination control techniques, service connection technologies and logistic simulation modelling. The feasibility of the maintenance processes will be reliant on the maturity of these technologies and so it is expected that many of these will be demonstrated using some form of physical modelling at varying sizes to thereby achieve the desired TRL and IRL.
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Grant Deliverables ID R&D Deliverables Date Maintenance PEP17 and project schedule 2021 Precision High Mass Test Rig (PHMTR) concept design 2021 PHMTR engineering/detail design 2022 Vertical Port Test Rig (VPTR) concept design 2022 Design for Maintenance Manual R&D report (annual) 2022 Supply and assembly of PHMTR 2023 Proof of principle (PoP) blanket handling system concept design development report 2023 Cryostat maintenance infrastructure outline RHE design development report 2023 Pipe chutes and chases maintenance infrastructure design development report 2023 Maintenance Management Plan (draft) 2024 Tokamak component maintenance feasibility assessments (blankets, divertor, limiter, shielding, pipe 2024 modules, etc.) Tokamak component maintenance outline remote handling equipment (RHE) design development 2024 report Tokamak building plant systems (ex-bio-shield) generic maintenance infrastructure: outline RHE design 2024 development report Supply and assembly of Horizontal Port Test Rig (HPTR) 2024 G2 gateway review documentation pack 2024 Supply and assembly of VPTR 2025 Supply and assembly of divertor cassette PoP end-effector 2025 RHE operation and control feasibility/trials report 2025 Pipe module handling trials report 2026 VPTR phase 1 trial results 2026 Pipe connection trials report 2026 Transporter digital twin (modelling tools demonstrator) version 1.0 2026 Maintenance Management Plan version 1.0 2027 Design for Maintenance Manual version 1.0 2027 Integrated upper port RHE concept system design descriptions (SDD) and maintenance process 2027 summaries (MPS) (limiters, shielding, diagnostics, pipe modules, port closure plates etc.) Integrated lower port RHE concept SDDs and MPSs (limiters, shielding, diagnostics, pipe modules, port 2027 closure plates etc.) Divertor cassette handling trials report 2027 Integrated plant maintenance RHE concept/outline SDDs and MPSs 2027 G3 gateway review documentation pack 2027
Grant Milestones ID Milestones Date PHMTR commissioned 2023 PHMTR phase 1 performance evaluation results 2024 Concept blanket handling system 2027 VPTR commissioned 2025 VPTR phase 1 performance evaluation results 2026 Outline concepts of vertical port remote handling equipment (RHE) and maintenance process summaries 2024 (MPS) Concepts of vertical port primary RHE and MPS 2027 HPTR commissioned 2024 HPTR phase 1 performance evaluation results 2026 Outline concepts of horizontal port RHE and MPSs 2024 Concepts of horizontal port primary RHE and MPSs 2027 Verified reactor pressure vessel inspection strategy 2025 Outline concepts of equatorial port RHE and MPSs 2024 Concepts of equatorial port primary RHE and MPSs 2027
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ID Milestones Date Tokamak building plant system maintenance trial results 2024 Pipe chutes and chases maintenance scheme trial results 2023 Outline concepts of RHE and MPSs for tokamak building plant rooms and systems maintenance 2024 operations Concepts of primary RHE and MPSs for tokamak building plant rooms and systems maintenance 2027 operations Portfolio of pipe connections 2026 Control system safety case justification 2027
International Collaboration Country Description of Collaboration To be defined
Industry Name Description of Collaboration TBC Design, assemble, and commission “Vertical Port Test Rig”, transporter/s, and end-effectors TBC Design, assemble, and commission “Horizontal Port Test Rig”, transporter/s, and end-effectors TBC Design, assemble, and commission “Precision High Mass Test Rig”, transporter, and end-effectors TBC Remote handling technology R&D (e.g. service connections, control, contamination, control, RPV inspection, etc.)
Use of Facilities Facility Status Scope of Use Year Name (New/Upgrade/ Commissioned) TBC New To house the test rig (VPTR) used to perform R&D development and 2025 - 2027 verification trials for a vertical port architecture TBC New To house the test rig (HPTR) used to perform R&D development and 2024 - 2027 verification trials for a horizontal port architecture TBC New To house the test rig (PHMTR) used to perform R&D development and 2023 - 2027 verification trials for large component handling (e.g. blankets) AIM-TU Commissioned The development of automated maintenance technology 2021- 2027 TARM Commissioned Technology R&D and remote handling compatibility assessments 2021 - 2027
Main Risks Risk Description Risk Impact Mitigation Strategy Insufficient FP9 budget for a Increased risk of architectural changes to the Select more maintainable plant verified conceptual design plant layout during the engineering design architecture. Reduce maintenance phase burden and requirements. Focus the work plan on areas of highest risk. Delay engineering phase. Lack of consortium Less mature components and RH equipment Encourage RU engagement through a members (RU) financial designs, and verification of tokamak balance work plan of technology R&D, support maintenance concept design and integration to improve the business case for investment. Delay engineering phase. Phasing of RU financial Less mature components and RH equipment Early identification of the most critical support inconsistent with designs, and delays to verification of tokamak element and ensure these are priortised. the work plan maintenance
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Risk Description Risk Impact Mitigation Strategy Lack of experienced/expert Poor maintenance strategies and weak Established lead engineering based RH engineers component and RH equipment designs collaborative hub with nuclear experienced industry supply chain. Lack of facilities to house Reduced R&D programme to verify tokamak Investment in an RMTF for fusion or test rigs maintenance alternatively fund the RUs to house such facilities (current rules too complex and do not allow for pro rata cost recovery). Lack of support for the Reduced R&D programme to verify tokamak Improve the funding model for the hardware maintenance hardware and its follow-on use and maintenance. Lack of industrial Reduced R&D programme to verify tokamak Develop a fusion maintenance supply engagement maintenance chain
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18 Materials (WPMAT, incl. MAT-TBM collaboration) Objectives - MAT The main scope of the work package materials (WPMAT) is to develop and qualify three baseline materials, i.e. EUROFER steel for blankets, tungsten as plasma facing armour material, and copper- chromium-zirconium (CuCrZr) for divertor heat-sinks. In addition, as risk mitigation, the development, characterisation and industrialisation of a few advanced materials with improved operational performance, i.e. radiation resistance, improved design, etc., remains a basic part of the strategy. The specific objectives are to: Carry out a vigorous n-irradiation program in suitable Material Test Reactors on the reference materials and for conditions relevant to the design. This includes Post Irradiation Experiments (PIEs) to measure resulting material property changes. Fabricate on industrial scale baseline materials and qualify them as well as the joining technologies under fusion environment conditions, in particular with regard to high heat flux performance and fusion neutron irradiation induced property changes. Implement data in the Material Property Handbook (MPH) and as appendices to Codes & Standards (RCC MRx...). Develop DEMO specific design rules for radiation loaded components and implement dedicated DEMO Design Criteria (DDC) including the assessment of fusion neutron irradiation effects by multi-scale modelling. Select advanced material concepts for risk mitigation, with continued development and characterisation towards industrial manufacturing and MPH implementation. Objectives – MAT/TBM The ITER TBM is a nuclear pressure equipment, which implies nuclear safety regulatory obligations and conformity assessment. A full characterization of EUROFER-97 for TBM application in ITER still needs to be done. This activity encompasses four major elements: o Design Rules: verification and completion of RCC-MRx design criteria (technical reference for TBM design) for EUROFER-97 including identification of material limits. o Experimental campaigns in support of design rules verification. o Experimental campaigns for EUROFER97 base material characterization to fill gaps in RCC-MRx material appendix A3.19AS. o Experimental campaigns for various EUROFER97 welded joints to populate RCC-MRx appendix A9.J19AS.
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Description of work
WPMAT R&D G2 G3 2021 2022 2023 2024 2025 2026 2027
Engineering Data MPH input for G2 MPH input for G3 MPH 1st major update for G2 MPH 2nd update for welds MPH 3rd update for final designs MPH release for EDP
Integration Goal: Fill gaps in MPH Goal: Estimate reduction Goal: Provide data for G3 Goal: Working doc.
DDC report for BB & DIV down-selection DDC report for BB & DIV concept design Revise DDC 1st development phase Development & validation phase Final DDC for EDP roadmap
Goal: Verification Goal: Systematically decrease uncertainties Goal: Guideline (
EDDI Goal: Set priority & &
Design Small-scale testing guidelines
) Standardisation SSTT – shape & methodology Small scale testing validation for RAFM steels report Goal: Define set of samples Goal: Irradiation test validation Input to
ENS Steel Dev Qualification Risk-mitigation steels decision Risk mitigation steels baseline st
( Fabrication of risk mitigation steels 1 phase characterization Irradiation phase Final report on progress SDQ
Goal: Fabrication (Ton volume level) Goal: Prepare for selection Goal: Towards decision point )
. . ODS steels pre-fabrication studies ODS steels at industrial scale (ton) Preliminary irradiation phase & & Goal: Industrial support Goal: Fabricate semi-finalized product Goal: Characterization
Flux Materials Down-selection of HHFM Decision on risk mitigation HHFM
High Heat (
HHFM Industrial fabrication risk mitigation material Non-irradiation test campaign First irrad. data report Final report on risk mitigation Goal: Upgrade manufacturing readiness Goal: Input for selection
) Additive manufacturing tech. for HHFM Additive manuf. of Goal: Test for decision point tungsten & CuCrZr
Materials Industrial fab. of DC & HCD materials
Functional Goal: Fill MPH database gaps Irradiation campaign Electrical insulators (IVC) R&D & fab. Goal: Qualification of selected materials in 1st phase st
( Goal: 1 charaterisation before
FM Final report irradiation campaign Qualification of DC candidate materials 2nd batch of irradiation
Goal: MPH )
update
(
Irradiation
Modelling IREMEV
Identification & development of models Mechanical property changes due to fusion neutron irrad. Neutron effects for in-vessel comp.
Goal: Selection of predictive models for effects Goal: Report on predictive capacity & assessment Goal: Technical guidelines )
Irradiation nd
( Neutron
IRRAD Sequentially launched irradiation campaigns for screening & MPH / DDC 2 round of irradiation campaigns Goal: Engineering data for DIV/BB design Goal: Input to engineering database for EDP
1st PIE campaign samples testing (incl. FP8) 2nd PIE campaign samples testing (for G3) Status report & EDP decision ) Goal: Close gaps in MPH for G2 Goal: Support MPH & DDC Goal: EDP working doc
Design Rule Validation High priority Design Rule Validation Full HP validation phase Goal: Test campaign Goal: Data for hazard analysis
Medium priority experimental campaign Full validation phase
MAT Goal: Complete data for hazard analysis Goal: Final TBM qualif. in 2029
High priority irradiation & PIE phase - TBM Programme Goal: Test campaign
Medium priority irradiation & PIE phase PIE final characterization Goal: Intermediate evaluation in 2025 Goal: Final TBM qualif. in 2029 Baseline characterization High priority qualification campaign PIE final characterization Goal: Complete data for hazard analysis Goal: Final TBM qualif. in 2029
1st phase weld characterization 2nd phase characterization Goal: Intermediate evaluation in 2025 Goal: Final TBM qualif. in 2029
st 1 phase irradiation tests & PIE Weld characterization Goal: Intermediate evaluation in 2025
MAT Down selection of options tech Joints & coatings Non-irrad. characteristics & definition Non-irrad. & irrad characteristics Joints, coatings & barriers charact. st nd - Goal: Needs defin. Goal: 1 intermediate report Goal: 2 intermediate report Goal: Final report for G3
NB: Indicates input to WPBB & WPDIV NB: Medium & High are defined by TBM hazard analysis
Grant Deliverables Deliverable ID Title (short description) Date MAT.T.D01 PEP 31.12.2021 MAT.T.01-D02 Report on DDC development and validation and update of DDC for down-selection 30.06.2023 of BB and DIV design options (G2) Page 103 of 143
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Deliverable ID Title (short description) Date MAT.T.01-D03 Major update of MPH on baseline materials for engineering down-selection (G2) 30.06.2023 MAT.T.01-D07 Report on DDC development and validation and update of DDC for evaluation of BB 30.06.2026 and DIV conceptual design (G3) MAT.T.01-D08 Major update of MPH for evaluation of conceptual design (G3) 30.06.2026 MAT.T.01-D09 Final report and DDC release for engineering design phase 31.10.2027 MAT.T.01-D10 Final report and MPH release for engineering design phase 31.10.2027 MAT.T.01-D11 Report on definition of small size testing methodology and respective sample 30.06.2022 shapes for RAFM steels MAT.T.01-D13 Report on small scale testing guidelines and progress towards standardization 31.10.2027 MAT.T.02-D01 Report on additive manufacturing technologies for steel fabrication 31.12.2022 MAT.T.02-D06 Final report on risk-mitigation steels progress 31.10.2027 MAT.T.03-D02 Report on industrial fabrication of risk-mitigation high heat flux materials 30.06.2023 MAT.T.03-D05 Final report on risk-mitigation high heat flux materials 31.10.2027 MAT.T.04-D02 Report on irradiation qualification of functional materials 30.06.2025 MAT.T.04-D03 Final report on functional materials 31.10.2027 MAT.T.05-D01 Report on theories and models to best estimate degradation of properties for BB 31.12.2023 and divertor materials for the foreseen operation durations MAT.T.05-D03 Technical guidelines for best estimates of fusion neutron effects for in-vessel 31.10.2027 components MAT.T.06-D01 Intermediate report on neutron irradiation campaigns including PIE from FP8 31.03.2023 irradiations MAT.T.06-D04 Final report on neutron irradiation campaigns on risk-mitigation materials 31.12.2026 MAT.T.06-D05 Report on divertor baseline materials irradiation campaigns & PIE 2027 for G3 and 31.10.2027 divertor EDP MAT.T.06-D06 Final report on neutron irradiation campaigns on EUROFER97 for G3 and BB EDP 31.10.2027 MAT.T.07-D05 Report on high priority non-irradiation characterization 30.06.2025 MAT.T.07-D06 Report on high priority validation of design rules 31.12.2025 MAT.T.07-D08 Report on high priority tasks on EUROFER97 welds 31.12.2025 MAT.T.07-D10 Report on neutron irradiation campaigns and PIE 31.12.2027 MAT.T.07-D11 Interim report on EUROFER97 welds characterization 31.12.2027 MAT.T.08-D01 Report on qualification needs for joints, barriers and coatings in BB and DIV 31.12.2021 MAT.T.08-D04 Final report on characterization of joints, barriers and coatings for G3 31.10.2027
Grant Milestones Milestone ID Title (short description) Date MAT.T-M04 DDC for BB & DIV down-selection at G2 30.03.2023 MAT.T-M05 Neutron irradiation data for baseline materials for MPH (G2) 31.03.2023 MAT.T-M06 Decision on additive manufacturing of tungsten & CuCrZr 30.01.2023 MAT.T-M10 Decision on risk mitigation steels 31.12.2024 MAT.T-M11 Decision on risk mitigation HHFM 31.12.2024 MAT.T-M12 Design rule validation 31.12.2025 MAT.T-M13 High priority data from TBM baseline characterisation for licensing 30.12.2025 MAT.T-M15 High priority data from TBM weld characterisation for licensing 31.12.2025 MAT.T-M18 Set of design rules for BB & DIV concept design validation 30.06.2026 MAT.T-M19 Non-irradiated and irradiated input data for baseline materials for MPH (G3) 30.06.2026 MAT.T-M20 Small-scale testing guidelines for RAFM steels 31.12.2026 MAT.T-M22 Decision on risk mitigation steels for EDP 30.11.2027 MAT.T-M23 Decision on risk mitigation HHFMs for EDP 30.11.2027 MAT.T-M25 Decision on MAT-tech. options for EDP 30.11.2027
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International Collaboration Country Description of Collaboration RF Neutron irradiation of structural materials up to 50 dpa RF Modelling of fusion neutron irradiation effects (material segregation) US Neutron irradiation of structural materials with emphasis on He-transmutation effects JP Material Property Handbook (MPH) for EUROFER97 / F82H, tungsten and CuCrZr JP Development of DEMO specific structural design criteria JP Modelling of fusion neutron irradiation effects (dose rate & He/H transmutation)
Industry Name Description OCAS Steel development and fabrication CSM Steel development and fabrication Zoz GmbH ODS-steel development and fabrication Louis Renner Fabrication of Cu-based heat sink materials XXX Development and fabrication of self-passivating tungsten XXX Fabrication of tungsten based plasma facing materials for the strike point region of the divertor XXX Material characterization for MPH AFCEN Design Criteria Development Woods Design Criteria Development Framatome Design Criteria Development
Use of Facilities Facility Name Status (New/Upgrade/Commissioned) Scope of Use Year BR2 Commissioned Neutron irradiation 2021-2027 HFR Commissioned Neutron irradiation 2021-2027 LVR-15 Commissioned Neutron irradiation 2021-2027 BRR Commissioned Neutron irradiation 2021-2027 Jules-Horowitz- New (availability not yet clear, under Neutron irradiation ? – 2027 Reactor (JHR) construction) HFIR Commissioned Neutron irradiation 2021-2027 BOR-60 (FBR) Commissioned Neutron irradiation 2021-2025 JOYO Under Refurbishment; expected Neutron irradiation 2022-2027 availability 2022 DiFU Commissioned Ion irradiation 2021-2027 JANNuS Commissioned Ion irradiation 2021-2027 JUDITH 2 Commissioned HHF testing (e-beam) 2021-2027 GLADIS Commissioned HHF testing (neutron beam) 2021-2027 PSI-2 Commissioned HHF testing (laser) 2021-2023 JUDITH 3 New HHF testing (e-beam, also irradiated 2023-2027 materials and components) HADES New HHF testing (e-beam) 2021-2027
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Main Risks Risk Description Risk Impact Mitigation Strategy Shut down of irradiation Delay of provision of data for neutron Distribution of irradiation campaigns on all facility or facilities irradiated materials lack of data for suitable and available irradiation facilities MPH and DDC worldwide
Launch irradiation campaigns as soon as promising materials are identified Inappropriate EUROfusion Impossibility to launch irradiation Administration informed and dealing with funding scheme for campaigns for facilities needing 100% possible options (also for FP9) irradiation facilities funding. Lack of data for timely selection of materials for design. Design cannot be realized Search for alternative options creates a Development of risk mitigation materials with one or more of the three delay in material qualification baseline materials Failure of selected risk Restart of material development Continuation of development for mitigation materials program; fallback to baseline materials promising material candidates until a high only with restricted operational quality selection process based on a performance sufficiently large dataset is possible Lack of interaction with Missing information on design options Point of contacts with others WPs (WPBB, design teams leads to delayed development of risk WPDIV,...) identified. PLs and Lead mitigation materials. Engineers systematically invited to WPMAT reviews Alternative design rules are not used by designers, leading to potential exclusion Dedicated benchmarking tasks defined of viable designs with contact points in WPDIV and WPBB. Lack of resources to perform Delay of data for MPH and DDC G2 and Survey of EFLs to investigate interest in material characterization (in G3 may not be achieved / delayed participating and commitment of particular neutron irradiation) resources.
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19 Safety & Environment (WPSAE) Objectives The key objective of the work package Safety and Environment (WPSAE) is to ensure safety for the DEMO plant, which is obviously at the heart of all design choices in view of the licensing process. The steps towards this are as follows: Integrate the safety criteria in the design of the plant structures, systems and components. Follow the design and conduct safety analyses of any plant system verifying that the safety requirements are satisfied. Define the radioactive source terms versus time. Verify that the operational and accidental releases are inside the defined safety limits. Minimise the radioactive wastes, particularly those at higher radioactivity level. Extensively validate the tools necessary for the safety assessment. Prepare the documentation pack to support the conceptual design. Supporting F4E to perform safety analyses for the ITER WCLL Test Blanket Module.
Description of work
WPSAE R&D G2 G3 2021 2022 2023 2024 2025 2026 2027
LiPb-Water reaction tests
Explosions Experimental campaign finalization Goal: Quantification of H-production & pressure peak
W dust – O2/water reaction tests Critical temp. range defined Goal: Reaction rate characterisation
H-D-T – O2 reaction tests Maximum allowed Goal: Detonation threshold, pressure peak inventory map
Inventory Tritium retention tests control Campaign completion Goal: Quantification of T-ret. in W & other materials
In-VV dust & tritium inventory measurement development Diagnostics tuning Goal: Identification of suitable technique
code code V Integration of T-transport/diffusion model in to Melcor code Beta version of Safety Goal: T diffusion, distribution, and combination in the affected volumes integrated code
& Code development and qualification for LiPb ACPs inventory Input for experimental V Goal: Dose rate evaluation for releases and ORE campaign
Waste management Waste In-vessel material detritiation tests Waste storage for tritiated Goal: H/D-release characterisation from W, Eurofer, SS, CuCrZr waste optimization
Dust detritiation technology tests Selection of suitable Goal: H/D-release characterisation solutions Molten salt detritiation technology development Technical solution Goal: H/D-release characterisation proposal Steel-water leaching tests Industry feasibility Goal: Recycling vs secondary waste production evaluation
WPSAE Design G2 G3 2021 2022 2023 2024 2025 2026 2027
Plant safety Preliminaryreport safety Safety guidelines boundary cond. DEMO Operation agenda Source term inventories
construction Occupational radiation exposure Maintenance plan development determind Failure mode & Postulated initiating events selection Preliminary map of releases Final map of releases & effect analysis due to DBE & BDBE doses due to DBE & BDBE Preliminary accident analysis Final accident analysis Replacement & refurbishment strategy Waste management assessment Decommissioning plan Dismantling programme
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WPSAE TBM Safety G2 G3 2021 2022 2023 2024 2025 2026 2027
Neutronics TBM Activation maps Goal: Assessment of Neutronics, radiation transport & shielding Occupational radiation exposure
ITER WCLL TBM TBM WCLLITERSafety ORE ALARA Goal: ORE analyses to define collective dose for TBM maintenance Preliminary Deseign Review Source terms inventory Safety Codes Update Goal: LiPb-water interaction models dev
Source terms inventory SADL Update Goal: Activation corrosion products inventories in water and LiPb loops
Accident Selection and Analyses Goal: FMEA, Design Basis Accidents and Beyond Design Basis Accidents report Preliminary Deseign Review Update ITER RPrS TBM Final Design Review Update TBM Safety Report Radwaste management TBM waste management plan Goal: Waste characterization, inventory, classification
Grant Deliverables ID Deliverable Date SAE R&D Plan18 2021 GSSR vol. 1 (Plant safety guidelines) 2021 GSSR vol. 6 (Accident sequence identification) 2021 GSSR vol. 3 (Source terms inventories) 2022 ITER WCLL TBM FMEA Report 2022 Selection & reporting on molten salt detritiation technology 2023 GSSR vol. 4 (Occupational safety) 2023 ITER WCLL TBM Preliminary Safety Report 2023 Definition of critical temperatures for W dust-H2O reaction 2024 GSSR vol. 7, 8, 9 (DBE & BDBE & external hazards preliminary analysis) 2024 Definition of boundary parameters for Q2-O2 reaction control 2025 ITER WCLL TBM Accident Analyses Report 2025 Selection & reporting on dust & tritium diagnostics for DEMO 2026 Steel-H2O leaching industrial feasibility results & report 2026 GSSR vol. 11 (Radioactive waste completion) 2026 Dismantling programme 2026 DEMO Preliminary safety report - final 2027 ITER WCLL TBM Safety Report 2027
Grant Milestones ID Milestone Date ITER WCLL TBM Preliminary Design Review 2022 Characterisation of LiPb-water reaction in BB geometry 2024 DEMO Preliminary safety report 2024 H-D-T-O2 detonation threshold & maximum allowed inventory map 2025 ITER WCLL TBM Final Design Review 2025 In-VV dust & tritium diagnostics tuned 2026 Beta version of tritium transport/diffusion model – MELCOR integrated model 2026 DEMO Decommissioning Plan 2026 Update ITER WCLL TBM Safety Report 2027 DEMO Preliminary Safety Report Updating 2027
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International Collaboration Country Description of Collaboration US Fusion safety code development (Melcor-TMAP) US Safety assessments in support of DEMO design work US Waste management strategies
Industry Name Description tdb W dust - air/water reaction test tdb in-VV dust and tritium diagnostics development tdb Dust detritiation tecnology test tdb Steel-H2O leaching industrial feasibility tdb Decommissioning plan outline tdb Waste recycling processes optimization
Use of Facilities Facility Status (New/Upgrade/ Scope of Use Year Name Commissioned) Lifus 5 (Existing) LiPb-water reactions 2021-2024 Q-Pete (Existing) Tritium retention tests 2021-2024 H3AT (Existing) In-vessel material detritiation tests 2023-2026 Tbd-1 (Existing) W dust – O2/water reaction aimed at Reaction rate 2021-2024 characterization Tbd-2 (Existing) H-D-T - O2 reaction aimed at detonation threshold and pressure 2023-2025 peak characterization in DEMO environment
Main Risks Risk Description Risk Impact Mitigation Strategy Lifus 5 – overlapping with other Extension of the Coordination of the scopes in the different WPs planning experimental campaigns in the experimental campaign common experiments same facility for additional years Q-Pete – overlapping with other Extension of the Coordination of the scopes in the different WPs planning experimental campaign in the experimental campaign common experiments. Planning coordinated campaigns same facility for additional years with KIT experiments out of the EUROFUSION frame H3AT – overlapping with other Extension of the Planning coordinated campaigns with CCFE experiments experimental campaign in the experimental campaign out of the EUROFUSION frame same facility for additional years Tbd-1 – Delay if the new facility Results obtained not in Moving up investigation for existing facilities to be has to be built from scratch the due time adapted Tbd-2 - Delay if the new facility Results obtained not in Moving up investigation for existing facilities to be has to be built from scratch the due time adapted
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20 Early Neutron Source (WPENS) Objectives For this Work Plan it is assumed that, during FP9, the construction phase of the DONES facility will be started on the reference EU site (Granada, Spain). As a consequence, a Project Team will need to be established to conduct the Construction Phase of the facility. The WPENS activities will be focused on completing the engineering design of the different systems of the facility, on providing support to the Project Team in those transversal activities with a long-term impact and in preparing the operation phase. The latter activity will include developing operational expertise in running a number of facilities relevant for different processes that will take place in DONES (some of which are already available, like LIPAc in Japan, while others will be built in the framework of the work package). The main objectives for the 2021-2027 period are: To complete the engineering design of DONES, to be transferred to the Project Team in charge of the construction of the facility. Prototyping and qualification of systems and components required for the DONES construction. Support to LIPAc operation in order to get operation feedback and develop (and integrate in the design) operational expertise for DONES. Develop engineering activities with focus on transversal activities with impact on long-term aspects of DONES including operation (safety, neutronics, maintenance, remote handling, RAMI -reliability, availability, maintainability and inspectability- analysis, control,….). Project Integration (including complete requirements identification and management, complete interfaces definition and management, CAD integration,…) as well as definition and implementation of a proper quality system. Support to licensing and permitting processes and CODA planning. These activities will be carried out by the Research Units and by Industry partners, partly included in a dedicated industrial framework.
Description of work DONES engineering Design: Update Buildings, Plant Systems, Lithium Systems and Remote Handling design up to the effective start of the Construction Phase. Complete the engineering design of Accelerator Systems (taking into account lessons learned from LIPAc operation) and Test Systems (with special emphasis on the recently proposed maintainable Test Cell concept). Complete the engineering design of Central Control Systems including safety-related operational limits and general facility performance ranges. Preparation of the Test and Commissioning Phase. Prototyping and qualification: Assess and identify in a systematic approach the prototyping and qualification needs and requirements in the Plant. Develop an experimental programme for the LIFUS6 facility. Construct and exploit a Li loop to demonstrate the Li purification procedures and the related components. Develop an experimental program for the validation of sensors and diagnostics (i.e. Li target diagnostics, neutron sensors and detectors, impurities sensors,…).
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Construct and testing prototypes of some key components such as: High Flux Test Module (HFTM), Start-up and Monitoring Module (STUMM), high-beta resonant cavity, Target Assembly, Quench Tank, Solid State High Power RF source, … Upgrade and exploit a facility for Li Safety evaluation. Upgrade and exploit the DRP Remote Handling facility. Support to LIPAc: Developm a mirror-control room of LIPAc in EU. Assess the possible use of the LIPAc facility for the qualification of DONES components and systems. Develop a specific effort to identify lessons learned and integrate them in the DONES design and operation phase. Transversal activities: Prepare the Safety Analysis Report (SAR) after the last version of the Preliminary SAR and taking into account the engineering design evolution and requirements of the radiological licensing frame. Progress in Probabilistic Safety Analysis (source term and fire areas) in support of licensing deterministic analysis. Further develop and adapt neutronics tools and nuclear data taking into account specific commissioning and operation needs. Prepare the scientific exploitation of the facility, linked to the needs arising from the DEMO design. Continuous update neutronics models and calculations according to design and safety progress and related requirements. Prepare a detailed Logistics and Maintenance Plan to optimize availability including the identification of the spare needs and maintenance policies. Optimise Remote Handling tools and operations to enhance availability. Optimise design on the basis of RAMI estimates. Waste management. Project Integration: Consolidate a configuration management system. Systematic update the Plant and Systems requirements. Continuously update the Plant layout (3D Model). Detailed definition and systematic update of interfaces between systems. Update of Codes and Standards applied (and to be applied) in the design of the different systems as well as development of a number of Handbooks. CODA planning: Prepare an integral Project Management Plan (PMP). Periodic update of the PMP chapters related to Commissioning and Operation activities. Prepare a Quality Assurance Plan (QAP). Periodic update of the QAP chapters related to Commissioning and, Operation Phases. Cost estimates updates. Provide support to licensing and permitting processes by preparation of specific technical studies
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WPENS
2021 2022 2023 2024 2025 2026 2027 engineering engineering
DONES Buildings, plant systems, lithium design systems, remote handling Accelerator & test systems
Control systems
qualification Prototyping New facilities construction
& & Facilities exploitation (LIFUS6, n_TOF, DRP, MARIA, HELOKA, RF lab, SUPRATECH, Li purification loop, Li safety,...)
Prototype fabrication and testing (HFTM, STUMM, resonant cavity, TA, QT, RF source,...) Support Support
LIPAc Mirror control room to
Use of LIPAc & operational expertise
Safety and neutronics for licensing & Safety and neutronics for operation
Transverse design activities Logistics, RAMI & maintenance for construction Logistics, RAMI & maintenance for operation
Remote handling & waste management for Remote handling & waste management for construction operation
Technologies for exploitation (module engineering, SSTT, modelling)
integration Project Project Configuration management & CAD modelling
Requirements & interface management
planning CODA Management & quality during construction phase Update for commissioning phase Update for operation phase
Cost estimate
Grant Deliverables ID Title (short description) Date D01 Integral Project Management Plan and Quality Assurance Plan 30/12/2021 D02 Update of IFMIF-DONES Engineering Design Report – v1 30/06/2022 D03 Boundaries and Interfaces Report including design review of Interfaces 30/06/2023 D04 Cost Estimate update 30/12/2023 D05 Maintenance Plan update 30/12/2024 D06 Update of IFMIF-DONES Engineering Design Report – v2 30/12/2024 D07 Summary of experimental validation activities and consequences on IFMIF-DONES Design 30/06/2025 and Operation D08 Integrated 3D Model 30/06/2025 D09 Update of IFMIF-DONES Safety Analysis Report 30/01/2026 D10 Update of summary of experimental validation activities and consequences on IFMIF-DONES 30/06/2027 Design and Operation D11 Update of Project Management Plan and Quality Assurance Plan in aspects related to 30/06/2027 Commissioning and Operation
Critical External Milestones ID Title (short description) Date EM01 DONES Construction Phase Start 31/12/2021 EM02 Positive results from LIPAc 31/12/2022 EM03 Environmental Permit Granted 31/12/2022
Grant Milestones ID Title (short description) Date
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ME01 Integral Project Management Plan and Quality Assurance Plan 30/12/2021 ME02 Boundaries and Interfaces Report 30/06/2023 ME03 IFMIF-DONES Final Engineering Design Report 30/12/2024 ME04 Integrated 3D Model 30/06/2025 ME05 IFMIF-DONES Safety Analysis Report 30/01/2026 ME06 Summary of experimental validation activities and consequences on IFMIF-DONES Design 30/06/2027 and Operation ME07 Project Management Plan and Quality Assurance Plan in aspects related to Commissioning 30/06/2027 and Operation
International Collaboration Country Description of Collaboration Japan Collaboration in Broader Approach Phase II, including support to LIPAc operation in Rokkasho, Test (QST and F4E) and Target Facilities activities and neutron source design
Industry Name Description Empresarios Contribution to DONES Codes and Standards, Safety Analyses, Plant Layout, detailed design of the Agrupados Main Buildings, design of conventional and safety related Plant Systems Visure Solutions Definition and management of System Requirements BTESA Prototyping and engineering design of the solid state RF source ESTEYCO Contribution to the engineering design of the Test Cell C3D Contribution to the engineering design of the Test Cell Ansaldo Nucleare Contribution to Lithium-related systems and technologies as well as Control Systems INETEC Remote Handling equipment and procedures Fuziotech Engineering support for Lithium and Test Systems Fortum Contribution to Safety Analysis
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Use of Facilities Facility Name Status Scope of Use Year (New/Upgrade/ Commissioned) SUPRATECH (France) Existing Testing of the high beta and low beta 2021-24 superconducting cavities (CEA) CIEMAT Materials Existing Validation of SSTT techniques (CIEMAT) 2021-27 Laboratory (Spain) High Power RF laboratory ??? RF systems (CIEMAT) 2021-24 (Spain) DRP facility (Italy) Upgrade Validation of main RH critical operations (ENEA) 2021-27 Lifus 6 (Italy) Existing Corrosion database production and testing of 2021-27 monitoring Lithium impurities monitors (ENEA) FLEX Helium loop Existing Tests of single irradiation rigs or capsules of the 2021-27 (Germany) HFTM, possibly endurance /lifetime tests (KIT) ??? New Li loop for demonstration of Li purification 2021-27 procedures ??? New Li safety issues (fire issues) 2021-27 HELOKA-LP Helium Loop Existing Tests of HFTM or STUMM prototypes under 1:1 2023-27 (Germany) helium conditions (KIT) Liquid Metal laboratory Existing Handling (filling, extraction) of Na and SSTT 2023-27 (Germany) specimens in capsules of HFTM (KIT) GALINKA gallium-indium-tin Existing Lithium Free surface detection (KIT) 2021-27 loop (Germany) MARIA reactor (Poland) Existing Irradiation campaign for components qualification 2021-27 (NCBJ) ??? New LIPAc mirror control room for training and R&D 2023-27 purposes (CIEMAT/UGR)
Main Risks Risk Description Risk Impact Mitigation Strategy Complex environment and agreements High Definition of the organization in charge, partners, roles and needed to implement the project responsibilities, governing structure Schedule constraints imposed by the High Planning of the time required for the licensing process, external organizations definition of procedure to use the structural funds Lack of unambiguous validation results Medium Continuous support to LIPAc activities, close collaboration from LIPAc with F4E and QST in LIPAc commissioning and collection of performance data relevant to DONES Different maturity of design status of Medium Priority given to design of systems in the critical path for DONES systems DONES construction, definition of boundaries and interfaces with such systems Lack of required expertise for design of Low Collaboration with engineering centers throughout Europe: unique advanced systems (e.g. liquid academic, laboratory as well as specialized industrial metal technology, tritium processing) companies, early identification of competences of partner institutions (NOTE: This high-level risk analysis has been made for the DONES project, not for the WPENS Workpackage activities. It has been made like this because we think the WPENS can not be analyzed separately in isolation of the other activities carried out in other projects)
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21 Prospective R&D (WPPRD)
Objectives Activities under Prospective R&D (PRD) are aimed at the delivery of commercially viable fusion energy, and at providing alternative, risk-mitigating, options for DEMO. Focus in research into promising alternative technologies that do not form part of the main DEMO programme due to their current readiness level or higher programmatic risk due to development uncertainty, but which offer the potential for improved reactor performance in the long-term. These alternatives may naturally, if achieved in time, be re-adopted into the DEMO programme. Additional aims of the (PRD) programme are: to identify long-term programmatic risks and start mitigation research, for example investigating fusion supply chains and wider industrial issues, and to study the scaling-up and industrialisation of production and processes. PRD, in general, is set to encourage innovation in the wider European fusion programme. Technology development work within PRD is generally overseen by the DEMO Project Leaders. The objectives in the Work Package PRD during Horizon Europe fall into a number of categories which: Advanced divertor concepts: integration of newly-developed materials (such as cold-rolled ductile tungsten) and joining techniques into a helium-cooled divertor design concept, along with the manufacture of small-scale mock-ups for qualification under representative high heat-flux (HHF) loading. Safety assessment of an integrated helium-cooled concept. Development of a heat-pipe target concept and evaluation of potential performance. Liquid metal divertors (LMD): development of prototype liquid metal plasma-facing surfaces and concepts for power-plant divertor cassettes – more below Tritium systems: continuation of the development of a continuous isotope-separation concept, and investigations into paths to lithium-6 enrichment. Magnet systems: development of high-temperature (HTS) winding pack options for tokamak magnets, including investigations of how to incorporate them into large toroidal-field coils. Development of HTS quench-protection modelling and identification of any additional materials requirements. Balance of plant: further investigation of alternative balance of plant cycles, primarily supercritical CO2 options. Breeder blanket: development of dual-coolant lithium lead (DCLL) concept, in particular the identification of specific requirements for the concept including permeation barriers, which may have cross-over applications in other power plant systems. Investigation of other blanket concepts (e.g. HCLL) where synergies allow. Advanced steels: scale-up manufacture of advanced steel and oxide-dispersion strengthened (ODS) steel, and further optimisation (composition, heat-treatment) of these steels taking into account advanced manufacturing methods. Materials modelling (IREMEV): use of advanced modelling techniques to develop macroscale tools for engineering use capturing the impact of fusion-spectrum radiation damage (e.g. input into finite element models) and to help guide the development of materials design rules and qualification. Heating and current drive: investigation of high-efficiency H&CD options such as photo- neutralisation and routes to incorporation into integrated systems. Tokamak power plant studies: development of systems codes to study the impacts of new technologies on power plant performance and economics. Investigation of impacts of system failure rates on overall performance to allow optimisation of maintenance strategies and plant layout as resources allow.
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Stellarator power plant studies (SPPS): development of parameterised magnet, blanket, and physics models to allow the engineering of stellarator power plant concepts to be explored, and the investigation of remote maintenance concepts for such plants – more below
In particular two of these – LMD and SPPS – are large areas and require some expansion. Mission 8 of the European Fusion Roadmap aims to bring the stellarator line to maturity focusing on the helical- axis advanced stellarator concept (HELIAS). In particular, the Roadmap foresees a review and decision point around 2030 on how to progress with a next-step stellarator device (such as a burning-plasma experiment). Apart from the key physics aspects for such a device, which will be explored by the Wendelstein 7-X experiment, there will be significant challenges for technology and engineering in the complex 3D geometry. SPPS will address the stellarator-specific engineering challenges in FP9 that are outside the scope of the tokamak DEMO activities. This will draw heavily on the knowledge embedded in the DEMO engineering and other synergies, hence the placement of this work here. SPPS will focus the R&D on the non-planar 3D magnet system (in particular in light of new superconductor technologies); neutronic analysis and integration of 3D breeding blanket technologies; remote maintenance and handling options and solutions in the complex 3D geometry; and integration of requirements for other components, such as divertor, fuel cycle, etc. Furthermore, SPPS will improve and carry out systems studies to explore attractive and feasible options for a burning-plasma next-step stellarator as well as HELIAS power plant. A persistent bottleneck in the stellarator engineering design optimization process is the availability of parametric models and/or tools, which can treat and handle the complex 3D geometry within reasonable time and resources. Consequently, SPPS will focus in FP9 on the development of parametric models and/or tools, which can be used to provide input for multi-physics analysis and FEM simulations. Present experience shows that the methods adopted for tokamaks do not work for sophisticated 3D stellarator geometry. SPPS will therefore be concerned with the development of appropriate stellarator-specific parametric models/tools for the magnet system, blanket, and vacuum vessel. First conceptual ideas for a remote maintenance scheme in stellarator geometry shall be developed utilizing the experience from the RACE team. Other elements such as the divertor and the tritium cycle will be explored on a conceptual level to assess stellarator-specific requirements and their impact on the overall stellarator plant design. The overall aim, by the end of FP9, is a coherent and feasible stellarator power plant concept. For the liquid metal divertor (LMD), in principle such a divertor can offer increased lifetime and robustness while handling a similar or greater steady-state power load compared to a fully-solid divertor. LMD works to develop this complex divertor technology and to ensure its compatibility with the core plasma and other technology systems to ensure high fusion power gain with resilient power exhaust. In FP8 a number of pre-conceptual designs conforming to the DEMO requirements were generated and the viability of the design strategy was validated in a gate review at the beginning of 2019, in which tin was chosen as the appropriate liquid metal and a number of plasma-facing pre-conceptual component options were reviewed. In FP9, the overall goal is to develop a coherent conceptual cassette design suitable for DEMO. An appropriate qualification strategy will be devised, in which the development of divertor modules suitable for use in dedicated tokamak test facilities such as COMPASS-U and DTT will play a central role. Prototype plasma-facing surfaces will be manufactured based on the agreed pre-conceptual design(s) and will be tested in several linear plasma devices and heat flux facilities. At least two rounds of prototyping are envisioned to enable experiential iterative improvement. This prototype development and testing will take place in parallel to the engineering design activities. Final/engineering designs for
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Version 6 May 2020 tokamak components will be developed to deliver tests in confinement conditions late in FP9. These will provide performance data, enabling modelling validation and extrapolation. Modelling aspects will also be important for understanding liquid-metal plasma interaction, in particular transport and power loss processes. Modelling of the liquid-solid interaction, capillary flow and the interaction of capillary-restrained liquid metals with plasma and electromagnetic forces is key in determining expected stability and impurity transport. For efficient divertor performance, the pumping efficiency of LM divertors must be evaluated. Codes will continue to be developed to incorporate the relevant atomic physics processes and self-consistent plasma-wall interaction. Modelling will span from core impurity accumulation to SOL transport and erosion and re-deposition under relevant plasma loading conditions, to give confidence in extrapolation to large-scale devices. Technologies for liquid metal confinement within the plasma facing component will also be developed to maximize performance as well as to identify the most cost-effective and scalable routes to large- scale production. Gaps in technical data on topics such as corrosion, bonding and wetting will therefore also be closed via dedicated laboratory experiments.
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Description of work WPPRD 2021 2022 2023 2024 2025
concepts Divertor Integration of helium-cooled divertor design concept Goal: small-scale high-heat-flux tests Heat-pipe target concept development Goal: Assessment of potential target performance
systems Tritium IR/PR - PSA experiments Goal: Full understanding of PSA ops, parameters, identification of materials Lithium enrichment - ICOMAX process demonstration Goal: HETP determination, performance of single-stage enrichment apparatus
systems
Magnet Magnet
HTS magnet options - winding pack, TF design issues Goal: HTS magnet concept, materials requirements identifications
Breeder blanket DCLL concept development and requirement capture Goal: Full understanding of further research requirements; identification of materials requirements HCLL concept development Goal: concept performance evaluation; identification of materials requirements
Advanced Scale-up of manufacture
steels Goal: Full understanding of further research requirements; identification of materials requirements Optimisation of steels Goal: concept performance evaluation; identification of materials requirements
modelling
Materials Development of macro-scale tools Goal: Full understanding of further research requirements; identification of materials requirements Input into materials design rules Goal: concept performance evaluation; identification of materials requirements
technology technology
options Further Advanced balance of plant options Goal: Full understanding of further research requirements; identification of materials requirements Heating and current drive Goal: concept performance evaluation; identification of materials
studies Power Power Systems code development
plant Goal: Full understanding of further research requirements; identification of materials requirements Power plant conceptual evaluation Goal: concept performance evaluation; identification of materials requirements
Stellarator Stellarator
studies Systems code development
plant Goal: parametric magnet and blanket models, physics basis Stellarator plant conceptdevelopment Goal: remote handling concept, divertor concept, fuel cycle analysis
divertor Prototype PFC construction and test
metal Liquid Goal: proof of principle, collection of performance data LMD cassette design Goal: COMPASS-U module build, DTT module design, DEMO concept
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Use of facilities W7-X, LHD (within International Collaborations). High-Performance computing (for e.g. Monte-Carlo simulations, materials modelling/IREMEV, LMD) For LMD prototype testing: AUG, COMPASS-U, DTT, linear plasma machines (Magnum-PSI, QSPA), high heat load devices (e.g. OLMAT) Opportunities for industrial innovation Non-planar superconducting coils for industrial applications. Bulk high temperature superconductors for industrial applications Advanced materials manufacturing and processing Development of porous matrices for high heat flux applications (c.f. heat pipes, EUV lithography sources) New materials and coatings with good compatibility with LMs (c.f. 4th generation nuclear fission) Development of novel microfluidic devices that incorporate the above properties Needs for theory/modelling development Multi-scale modelling of radiation-damage structures and the induced changes in materials properties and dimensions are being developed, and the whole scope of the IREMEV programme is to develop the theory behind these models and make macro-scale versions available. For stellarator conceptual design, theory and modelling support is required to facilitate the development of parametric models that can accurately reflect the complex 3D stellarator geometry. Furthermore, high performance computing is required for e.g. Monte Carlo neutronics analysis. LMD requires development of SOLPS codes: one particular complication can be the high impurity level present during vapour shielding which may invalidate some of the assumptions - this needs specifically addressing, such as the usage of the BGK model in EIRENE for neutral-neutral collisions.
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Deliverables ID R&D Deliverables Date Overall progress report for WPPRD 2021 Intermediate report on progress in stellarator engineering activities 2021 Improved LMD prototype(s) for HHL testing completed 2021 Overall progress report for WPPRD 2022 Advanced heating and current drive option assessment 2022 Intermediate report on progress in stellarator engineering activities 2022 COMPASS-U prototype LMD module 2022 Overall progress report for WPTPPS 2023 Progress of implementation of model-derived inputs to macroscopic materials property prediction 2023 Intermediate report on progress in stellarator engineering activities 2023 Overall progress report for WPTPPS 2024 HTS TF magnet design report 2024 Intermediate report on progress in stellarator engineering activities 2024 DTT prototype LMD module 2024 Overall progress report for WPTPPS 2025 Progress on scale-up of manufacturing of advanced steels 2025 Report on Li-6 enrichment process 2025 Report on multi-physics and neutronics assessment of the European blanket concepts in stellarator 2025 geometry Report on options for a feasible and attractive next-step stellarator as well as extrapolation to a 2025 stellarator power plant Report on requirements assessment for remote maintenance as well as for plant components such 2025 as divertor, tritium cycle, etc. in stellarator geometry COMPASS-U divertor LMD module 2025 DEMO LMD-divertor conceptual design including integration impact report 2025 Milestones ID Milestones Date Completion of initial LMD prototype testing in HHL devices 2021 HTS TF coil concept available for evaluation 2022 Completion of improved LMD prototype testing in HHL devices 2022 Complete manufacturing of COMPASS-U LMD prototype 2022 PSA experimental equipment procured and assembled 2023 COMPASS-U prototype LMD module testing completed (AUG and HHL) 2023 Initial availability of radiation effect tools in FE code 2024 Development of a prototype parametric coil model for stellarators 2024 Development of a prototype parametric blanket model for stellarators 2024 Complete manufacturing of DTT LMD prototype 2024 One separation stage for Li-6 enrichment demonstrated 2025 Bulk advanced steel samples produced 2025 Preliminary multi-physics and neutronics assessment of the European blanket concepts in 2025 stellarator geometry Systems studies exploring various options for a feasible and attractive next-step stellarator as well 2025 as extrapolation to a HELIAS power plant Requirements assessment for remote maintenance as well as for plant components such as 2025 divertor, tritium cycle, etc. in stellarator geometry DTT prototype LMD module testing completed (AUG and HHL) 2025 COMPASS-U divertor LMD module completed 2025 Conceptual Design Report for LMD for DEMO finalized 2025
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22 Socio Economic Studies (WPSES) Objectives The main objective of Socio Economic Studies work package is the identification of the economic and social conditions that could effectively support a wide fusion deployment in a future global energy market. While Social Studies investigate and assess current attitudes of lay public, stakeholders and media towards fusion technology, Economic Studies look at the future and provide different plausible scenarios of the global energy system in order to assess which role fusion could play. SES tasks are aimed at defining the economic and social measures fusion power must achieve to be commercially viable and, as such, could have effects on technology choices for DEMO. The research activities on social aspects of fusion will be aimed at monitoring public attitudes towards the technology and keeping a dialogue with energy experts and stakeholders belonging to both fusion and renewables community. Focus groups, surveys and analyses of social media will be the key tools for assessing the state of public knowledge and attitude towards fusion. The Fusion Expo will be a tool for assessing the effectiveness of new exhibition schemes in conveying complex concepts and form personal informed opinions. As for the Economic Studies, constant maintenance activities of the EUROfusion TIMES model (ETM) are envisaged so to keep the model in line with energy technologies evolution and policy recommendations from relevant energy and climate associations. New scenarios will be produced to broaden the area of analysis. Special attention will be paid to the relationship between the increasing penetration of renewables and power grid adequacy as well as to the key role nuclear fission is likely to play as bridge between nowadays and the time of fusion commercialization. Description of work The Economic and Social Studies will be carried out separately but interactions are envisaged between the two teams within SES as well as the EUROfusion communication team. Social Studies: A dialogue with energy experts and stakeholders will be pursued to monitor the effects of energy systems evolution, ITER progresses and international fusion research roadmaps on attitude and support towards both nuclear fusion and related research activities. Motivations in support or against possible approaches towards the global energy system decarbonisation will be analysed. The relevant outcomes will provide the basis for the development of new scenarios within the activities of Economic Studies. Experts on areas outside nuclear fusion (e.g. renewables) will be involved, in order to gather the widest range of perspectives on the issue. The attitude of the lay public towards fusion and the energy issue will be monitored by further European Surveys, following the successful survey carried out in 2018. Due to the limited knowledge about the fusion technology of the greatest part of the population, the survey can be used to study the effects of scientific and objective information on personal opinions shaping. As a consequence, this kind of survey would work as educational tool also. Because of the key role nuclear fission could have in bridging the gap between the current energy systems and future decarbonized energy systems relying on renewable and nuclear fusion power, the attitude of lay population on fission technology and energy policies in supporting fission phase-out will also be worth assessing. Economic Studies The EUROfusion TIMES model will be adapted to include the progressive energy technologies evolution as well as new recommendations from relevant energy and climate associations and related changes in national energy policies.
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New energy scenarios will be produced to investigate a wide range of possible evolution of global and national energy systems. Land use by renewables, actual rate of fusion capacity increase as a function of tritium production, nuclear fission phase out, biomass availability and related costs as well as CCUS (Carbon Capture Usage and Storage) actual deployment will be investigated and discussed in terms of the energy system set up. As renewables are likely to have gained a prominent role in the electricity generation mix once nuclear fusion will be a commercially viable option, the evolution of the electric grid necessary to accommodate the large share of distributed electricity from renewables deserves proper attention. Both technical viability and affordability of a range of possible electric grid developments and the requirement for relevant energy storage capacity will be studied through dispatch models as possible key factors of nuclear fusion deployment. Outreach activities Both teams also pursue an effective dissemination of the results. Besides the active participation to workshops and conferences, resources will be invested in keeping an effective communication through the web. Deliverables ID R&D Deliverables Date Report on input to Fusion EXPO 2021 Report on stakeholder consultation 2023 Report on socio-economic impact of ITER build, including on attitudes to fusion 2024 Report on updated energy market scenarios and modelling 2024 Overall report on public consultation exercises 2025 Milestones ID Milestones Date Stakeholder/expert consultation exercise 2021 Update of EUROfusion scenarios 2023 Second public attitude survey on fusion energy 2024
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3.4 Communications 23 Communications (WPCOMM) Objectives To be of value, communications must generate desired results is support of clearly and collaboratively set objectives. And these results must be tracked and reported back to stakeholders. This is at the heart of the new stakeholder consultation cycle the Communications Office will be adopting for Horizon Europe. Improving our ability to achieve valuable results is also a key objective for Horizon Europe. This entails properly structuring and resourcing the Communications Team, and constantly seeking to improve the effectiveness (impact) and efficiency (return on investment) of communication efforts. To realise these objectives, the Communications Office will begin a formal effort to continually refine its content and key messages, as well as targeted promotion and distribution efforts, through a new Content Marketing Strategy. Partnership and collaboration will help speed these efforts. Not only will we pull key learnings regarding targeted content and messages for target audience segments from large and experience communications teams such as at ITER and the UKAEA/CCFE, we will also collaborate with the Social Economic Studies (SES) team to develop and test messaging for segments – even by country. In turn, this will help us develop a more sophisticated and effective approach to communications – one which we will share with our Consortium partners through FuseCOM (the Fusion Communicators network). As such, the overall objective for communications activities during Horizon Europe is to better contextualise the relevance of the Programme and the efforts of Consortium Members by tailoring our approach (content, key messages, promotion, channels) for the following audiences: Citizens (of Consortium Member countries): desired outcomes include: a) raising awareness of fusion and European fusion research efforts: specifically EUROfusion, b) improving support for continued fusion research and EUROfusion funding by communicating the immediate and long term value of EUROfusion-directed fusion research efforts, and c) engage with citizens by increasingly encouraging debate, discussion and even seeking their input and guidance via the eventual adoption of a citizen-science practice. The new Fusion Expo traveling exhibition will become a key outreach and education tool for this segment. It has also been designed to capture extensive insights into visitors / participants, which will be used to improve existing and direct new outreach efforts. European Fusion Community (including Alumni): Internal communication efforts will be significantly scaled up for Horizon Europe, guided by a forthcoming stakeholder consultation and a resulting Internal Communications Strategy aimed at improving communications within the PMU (Culham and Garching) and comprehensively within the EUROfusion Consortium. Objectives include: better awareness of and alignment in pursuit of our common goal, improved adoption of a project management culture, and stronger identification with the EUROfusion brand (our purpose and values). Students and EUROfusion Fellows: By the end of 2020 about 80 researchers in the early stages of their career will have finished their term, having directly benefitted from the 10-15% of EUROfusion’s overall budget directed towards education. Ensuring they are aware and supportive of EUROfusion is a key objective. Efforts will be made to capture and share their stories, in order to attract more students (especially women) to pursue their studies and future careers in fusion.
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Industry: This segment is key to helping use realise the key steps in the Roadmap. They are also very influential politically. As such, it is in the interest of EUROfusion to promote the work, especially the successes and personal accounts, of industry partners and the immediate benefits they experience from fusion research and also resulting spin-off technologies. Journalists: A key objective for Horizon Europe is to raise the profile of EUROfusion and its beneficiaries (Consortium Members). Building relationships with journalists, and leveraging them along with press releases to greatly increase the reach of our achievements and successes, are part of an expanded media effort that will be adopted. Politicians & Public Sector: A key objective for Horizon Europe is to introduce a properly organised and run public affairs and lobbying effort with the express purpose of improving awareness and informed support of fusion energy, fusion research and the EUROfusion Programme and its Consortium Members within this, THE most important stakeholder segment. Targeted content will support the lobbying efforts and promote the value of fusion research in the short (return-on-investment, spin-offs, and technology transfer) and long- term (environmental and societal impact). Closer collaboration and better networking with the European Commission is foreseen, but the extent of this effort will come out of the new stakeholder consultation effort. Global Fusion Community: In line with EUROfusion’s collaboration beyond Europe’s borders and the communal spirit of the worldwide fusion research community, during Horizon Europe we will look at how the Communications Office can improve EUROfusion’s influence and presence globally.
Description of work Both the brand of EUROfusion and its messaging must be continually evolved and strengthened over the course of Horizon Europe. The Horizon 2020 focus on fusion devices appealed to technical and scientific audiences. It makes sense to continue this effort for these audiences. However to reach more people more effectively, the Communications Office will focus on new messages: the people working in fusion, their passion for fusion and achieving the impossible by realising fusion energy, and how the collaboration and diversity at the centre of the EUROfusion Programme is an example for the rest of the world. Messages include: Fusion research benefits: spin-off stories, opportunities for students, how fusion research is bolstering European industry, and technology transfer The Roadmap: its goals, impact and progress; ITER and DEMO timelines and missions Devices: the scientific exploitation of JET and the other devices, and the Broader Approach including JT60-SA Research Units: the vital role of individual Consortium members both locally and to the EUROfusion programme Fusion basics, the challenges ahead, and the progress achieved Dissemination strategies For fusion, especially due to its nuclear nature, public awareness and support matters. Reach a broader audience Since late 2019, the content on our external website (with the exception of our glossary) and many of our social media posts are in German
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Over the course of Horizon Europe, find a way to quickly and cost-effectively translate and release key news and content through our FuseCOM members to their local media Create and distribute content on other platforms such as European Commission channels, ITER Newsline, EPS newsletter, and online magazines Update and improve our use of social media in order to reach new audiences Curation and Outreach Create multimedia packages of content on key topics and for specific segments Ensure we promote each Research Unit Maximize impact of content by adapting different versions for specific target audience segments (also tracking and ensuring we have sufficient information for each specific target segment on key topics of interest/value to them) Use multiple channels and platforms to publish content Create conference-specific content Broaden our content curation efforts, giving the EUROfusion perspective on news and new developments while aiming to become a global hub for fusion news and information Fusion in Europe Over the course of Horizon 2020, Fusion in Europe magazine changed from an internal newsletter into a publication with externally-targeted content. During Horizon Europe, we will fully digitalise its content and focus efforts on ensuring its content reaches the general public. Part of a larger effort to more meaningfully and regularly connecting with our audiences, it will change from quarterly magazine to weekly or bi-weekly feature articles. The annual Fusion Writers’ Edition will continue, updated to be a major multimedia campaign aimed at reaching new audiences. The diversity of authors contributing to the new feature articles will also be expanded, reflecting the diverse and collaborative nature of EUROfusion, and our commitment to provide different points of view while better representing the unique approach and vision of the EUROfusion Programme. Traveling exhibition (Fusion Expo) Our new traveling exhibition employs ‘transmedia’, blending storytelling with virtual and augmented reality with art in a gender equal and inclusive approach. Divided into three parts, participants first explore the basics of nuclear fusion in libraries and through game-based learning before advancing to the second part in a museum exhibition that delves into the aspects of fusion research. In the third part visitors apply their knowledge in a participatory decision- making/debate exercise. Qualitative and quantitative visitor data is collected throughout for use in improving future content and for insights into public discourse. The Communications Office will organise and facilitate the following: Creating networks with libraries and cultural organisations as hosts to the exhibition and as mediators of our messages Creating thought-provoking content on societal aspects of fusion research and energy Creating educational material for schools (adapted to each country’s syllabus) Designing thematic conferences on women in physics and sciences with the help of the Gender & Inclusion Committee Organising events (artistic performances or guided visits) where artists themselves share their creative process
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Creating a Selection Panel and organise an Apprenticeship Design Challenge to identify novel ideas for hands-on exhibits Designing a writing workshop to identify alternatives to the transmedia storytelling Evaluating visitors’ feedback in collaboration with WPSES. This serves two purposes: (1) to constantly improve the exhibition and (2) to share public opinion with stakeholders Seeking partnerships with industry to build copies of the exhibition in order to increase visibility and presence in Europe. Research Units benefit from the exhibition by: Hosting the third part of the exhibition Co-creating content from a national angle Co-creating a cultural programme in their country Organising career-oriented visits for high school students, especially girls Facilitating debates and discussion on fusion-related topics with visitors after the participatory activity FuseCOM The Communications Office facilitates the network of communicators on fusion research (FuseCOM). The Head of each Research Unit selects a member of staff to act as their communication contact person. The Communications Office will consult with FuseCOM members in 2020, and use their feedback to evolve FuseCOM in order to constantly improve its value to Research Units over the entirety of Horizon Europe. Deliverables The list of deliverables has been dramatically changed from what was shared in Horizon 2020. This reflects the new Communications Office’s goals and approach of using an annual stakeholder consultation process to determine what communication efforts are actually required by the EUROfusion Programme, Consortium Members and other stakeholders. What is proposed below will be updated once the stakeholder consultation has been conducted successfully, and will continue to evolve over the course of Horizon Europe, reflecting a more proactive, flexible and ambitious-yet- reasoned approach to communications.
ID Deliverables Date Launch of new Communications Office in 2021 in support of Horizon Europe 2021 • Impact analysis and adoption of high-impact practice • Processes - document and optimize processes • Streamline existing websites and assets down to what is actually used and valued • Identify and adopt new KPIs/reporting metrics that speak to goals/desired results • Introduce new, brand- and goal-aligned promo items / giveaways • 1-page Communications Strategy; annual work-plan Social media – write strategy and update practices 2021 Strategic Content Marketing strategy written and adopted 2021 New digital-only transformation of Fusion In Europe into feature articles 2021 Internal Communications strategy written and adopted 2021 Relaunch more proactive FuseCOM effort aimed at better representing each beneficiary, all 2021 projects, and coordinating communication into each country/region Introduce Media and PR practice 2021 Prepare Crisis Communications strategy for internal stakeholder review 2021 Adopt Crisis Communications strategy 2022 Launch lobbying efforts 2022 FuseCOM in-person meeting (including training) Yearly Comprehensive Stakeholder Consultation to evaluate current efforts, identify needs and gaps Yearly Stakeholder Annual Report (internal and external versions) Yearly Fusion Expo – visiting 2 to 3 countries per year Yearly Conference Attendance – 2 to 3 conferences per year Yearly Page 126 of 143
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3.5 Training and education 24 Training and Education (WPTRED) Objectives Training and Education were for the first time an integral part of the joint European effort in fusion during Horizon 2020. Building on the success of these activities, the proposed Training and Education Programme under the EUROfusion Consortium during Horizon Europe aims at supporting PhD programmes in the fusion institutions and MSc student programmes across Europe, as well as at directly financing focused post-doctoral training programmes. EUROfusion provides support for the PhD programme in its beneficiaries on the basis of the recent past track records in PhD education in each of their research institution. The support for MSc programmes and the coordination of advisory missions to countries with developing fusion PhD Programmes are performed by FuseNet, the European Fusion Education Network. In this context, the specific role of FuseNet will be to assist the Consortium in the implementation of the peer review of the proposals on education by the different Consortium members, and in the monitoring of these educational activities. Members of FuseNet are universities with a fusion curriculum, fusion research labs as well as industries that are involved in fusion. FuseNet has defined joint criteria for the European fusion master and doctorate, coordinates the summer schools, acts as matchmaker for internships between students and industry, and organises joint educational events and tools. The possibilities in fusion education are made accessible to students via the FuseNet website www.fusenet.eu. The stimulation of FuseNet as a learning platform for all educational levels, should help increasing the pool of skilled people involved in fusion across Europe.
The EUROfusion Researcher and Engineering Grant Programmes are highly successful and will be continued in 2021-2027. They promote excellence among young researchers by competitively making available approximately 10 EUROfusion Researcher Grants (2-year postdoc grant) and 20 EUROfusion Engineering Grants (3-year training as engineer) per year. Measures to enhance the number of engineers in the fusion programme as it evolves towards greater emphasis on engineering and technological aspects will be undertaken.
Management: Programme Management Unit and FuseNet
Description of work
1. PhD and pre-doctoral Programme This programme provides a direct support to PhD and pre-doctoral projects in the fusion institutions and university student programmes across Europe, promoting excellence and an appropriate balance of the topics in fusion engineering and physics. The total number of PhD students in fusion must progressively grow to meet the needs of fusion as it enters the commercial era, depending on the need for PhDs in industry, which has to be assessed. It is important that the programme influence the development of fusion education to contribute to the development of human resources in fusion in line with the evolving roadmap. For this , the basis for high quality education across Europe should be widened, allowing students from all European countries to benefit from the breadth and quality of education within the laboratories and Universities that are linked to Consortium members. Creating a common ground in Europe will naturally increase the attractiveness of the fusion field for students. Page 127 of 143
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In order to strengthen the fusion links from laboratories and universities to industries, industry should be involved in the educational efforts. A job fair with possibilities for interviews could be organized in connection with the annual FuseNet PhD event. The Fusion Industry and Innovation Forum (FIIF), formed by industrial organizations that are involved in the development of fusion energy, shall identify industries with significant fusion business and EUROfusion and FuseNet shall help by advertising to them the event and encouraging them to participate. As an increasing number of fusion-related jobs will be in industry, the FIIF is essential in the formulation of the required competences and needs, which could then be provided by FuseNet and EUROfusion. The primary focus of FuseNet remains on MSc and PhD students. Nevertheless, it is important to stimulate fusion education also at earlier levels, to enlarge the potential pool of human resources, including improving the gender balance, and diversity in general. The recent past track record in PhD education in each research institution is evaluated from the actual number of PhD students and the number of PhD theses in fusion completed in the previous 5 years. To keep track of this on an annual basis, a PhD database has been set up by EUROfusion. The assistance to the Consortium for PhD education and the management of the undergraduate support require an organisation with established links with the Academic environment and proven experience in coordinating the education in fusion.
2. EUROfusion Researcher Grants The possibility of having prestigious post-doctoral fellowships, attributed on the basis of a competitive selection, is an important element of high-level training programmes. In the FP7 fusion research programme, EFDA implemented the Fusion Researcher Fellowship Programme. Following the recommendation made by the Ad-Hoc Group “Survey of Human Resources in the European Fusion Programme”, endorsed by the CCE-FU on 21 March 2007, the action aimed at “provid(ing) encouragement for excellence and career development by awarding grants similar to the Marie Curie type fellowships” (to which fusion researchers do not have access). In the period 2007-2013 six Fellowship Programmes were launched by EFDA and 57 grants were awarded. This programme has continued during Horizon 2020 as the EUROfusion Researcher Grants programme (a total of …. ERGs has been awarded). Based on the past success, it is planned to carry out this programme during Horizon Europe with the same format. Within the agreed format, the selection is made by a group of about six independent experts. Each eligible application is evaluated individually by two experts against the following criteria: quality of the thesis, research project, scientific publications, European/international background. The final scoring for this first step is agreed by the six evaluators. On the basis of this evaluation a shortlist of candidates is selected for an oral interview. Following the interviews a final selection for the fellowship award is made. During the period of the grant it is planned to encourage excellence and career development of researchers who are already in the programme or attract high quality potential candidates from outside the programme. The Researcher grants will be attributed at post-doctoral level or equivalent. They will cover the salaries of the selected candidates and part of the cost of their research activities and missions for the duration of up to 2 years. As for the EFDA Fellowship Programme, the Eligibility criteria have been elaborated according to the AHG Recommendations endorsed at CCE-FU, namely that “the competition should be as broad as possible, therefore all recently attributed post-docs … should be allowed to compete for this funding, although the proposals should be channelled through the Heads of Associations.” Thus, all candidates in possession of a doctoral degree and having started or starting a first post-doctoral or equivalent contract after PhD in a European fusion laboratory during the reference period are eligible as well as Page 128 of 143
Version 6 May 2020 engineers with professional experience of at least 3 years and up to 5 years. The candidates shall work on a scientific or technical subject relevant to the Work Plan for the implementation of the Fusion Roadmap in Horizon Europe. “In view of ensuring the excellence of the selected fellowships and thereby creating a recognised “brand””, the Eligibility criteria have been elaborated according to the AHG Recommendations endorsed at CCE-FU, namely that “the fellowship should be awarded according to the sole exceptional quality of the candidate and his/her proposal.” A Call will be issued every year with the goal of awarding about 10 Grants per year.
3. EUROfusion Engineering Grants An approach similar to the Researcher Grants is envisaged for the Engineering activities, to replace the former GOT scheme. The EUROfusion Engineering Grants programme, which has already proved successful in Horizon 2020, encourages excellence and career development of young engineers who are already in the programme or attract high quality potential candidates from outside the programme. The training areas will be defined by the Programme Manager in consultation with the Work Packages’ Project Leaders/Task Force Leaders. The EUROfusion Engineering Grants will be awarded at post-master and post-doctoral level. They will cover the salaries of the selected candidates and part of the costs of their research activities and missions for a duration of up to 3 years.
In addition to the traditional forms of the Engineering Grants the option of “shared” or “joint” Engineering Grants shall be investigated and tested, in which students spend a (large) part of their works in industrial companies which have multi-year contracts in fusion technologies. The benefit of this new approach shall be threefold, giving students a sound perspective for a later job in fusion technology in industry, supporting the tendency that fusion students stay in fusion and strengthening the links between laboratories, universities and industrial companies.
A Call will be issued annually with the goal of awarding about 20 Grants per year.
Deliverables
ID R&D Deliverables Date Implement the PhD and pre-doctoral work programme with FuseNet in 2021 2021 Implement the PhD and pre-doctoral work programme with FuseNet in 2022 2022 Implement the PhD and pre-doctoral work programme with FuseNet in 2023 2023 Implement the PhD and pre-doctoral work programme with FuseNet in 2024 2024 Implement the PhD and pre-doctoral work programme with FuseNet in 2025 2025 Call for the Fellowship Programme 2022-2023 2021 Call for the Fellowship Programme 2023-2024 2022 Call for the Fellowship Programme 2024-2025 2023 Call for the Fellowship Programme 2025-2026 2024 Call for the Fellowship Programme 2026-2027 2025 Interim Report for the Fellowship Programme 2021-2022 2021 Interim Report for the Fellowship Programme 2022-2023 2022 Interim Report for the Fellowship Programme 2023-2024 2023 Interim Report for the Fellowship Programme 2024-2025 2024 Interim Report for the Fellowship Programme 2025-2026 2025 Final Report for the Fellowship Programme 2020-2021 2021 Final Report for the Fellowship Programme 2021-2022 2022 Final Report for the Fellowship Programme 2022-2023 2023 Final Report for the Fellowship Programme 2023-2024 2024 Page 129 of 143
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Final Report for the Fellowship Programme 2024-2025 2025 Call for the Engineering Programme 2022-2024 2021 Call for the Engineering Programme 2023-2025 2022 Call for the Engineering Programme 2024-2026 2023 Call for the Engineering Programme 2025-2027 2024 Call for the Engineering Programme 2026-2028 2025 First Interim Report for the Engineering Programme 2021-2023 2021 First Interim Report for the Engineering Programme 2022-2024 2022 First Interim Report for the Engineering Programme 2023-2025 2023 First Interim Report for the Engineering Programme 2024-2026 2024 First Interim Report for the Engineering Programme 2025-2027 2025 Second Interim Report for the Engineering Programme 2020-2022 2021 Second Interim Report for the Engineering Programme 2021-2023 2022 Second Interim Report for the Engineering Programme 2022-2024 2023 Second Interim Report for the Engineering Programme 2023-2025 2024 Second Interim Report for the Engineering Programme 2024-2026 2025 Final Report for the Engineering Programme 2019-2021 2021 Final Report for the Engineering Programme 2020-2022 2022 Final Report for the Engineering Programme 2021-2023 2023 Final Report for the Engineering Programme 2022-2024 2024 Final Report for the Engineering Programme 2023-2025 2025
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3.6 Management TEXT BELOW IS FROM FP8 PROPOSAL AND WILL BE REVISED IN THE NEAR FUTURE AS IT WAITS FOR WG3 TO DELIVER
25 WPPMU: Programme Management Unit
Work Package 33 Start Date or Starting Event 01. Jan 14 number
Work Package title Programme Management Unit (WPPMU)
Short name of Participant Number Person-months per Participant: participant 29 CCFE 645,48 0,00 11 CEA 100,80 0,00 26 CIEMAT 132,36 0,00 16 DIFFER 54,96 0,00 17 ENEA 234,96 0,00 28 EPFL 12,00 0,00 12 FZJ 220,92 0,00 22 IST 165,96 0,00 13 KIT 247,92 0,00 3 LPP-ERM-KMS 60,00 0,00 1 MPG 1.008,96 0,00 2 OEAW 19,92 0,00 10 VTT 28,80 0,00 15 Wigner RCP 12,00 0,00 N/A z_Not allocated 12,00 0,00 2.957,04 Objectives The management of the Consortium programme involves two entities the Programme Management Unit and the Coordinator Unit. The Programme Management Unit supports the Programme Manager in the implementation of the Programme of the Consortium and ensures that common standards based on good project management practices are followed in all the projects for the selection of the participation, the management of the activities, the documentation and the evaluation of the accomplishments. The role and responsibilities of the Programme Management Unit are described in Chapter 4. Description of work As initial composition of the PMU the following structure, composed by three technical Departments (JET, ITER Physics and Power Plant Physics and Technology), the Administration Department and the Public Information Group will be used
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The Programme Management Unit will include both professional and host support staff. On top of this, a group of people will manage the JET Operating Contract within the JET exploitation Unit in Culham. A central asset of EUROfusion is the strategy to implement the programme with persons that are selected from applicants of all Beneficiaries. This applies to the Programme Management Unit, the JET Implementation Unit and to parts of specialized staff required for the Operation of the JET facilities. The Coordinator Unit supports the Coordinator to fulfil its obligations and in particular to liaise with the Commission services, the Programme Management Unit and the Consortium members in administrating the Consortium. The Coordinator Unit collects all relevant information and documents to be provided to the Commission for the administration of the Grant Agreement. The Coordinator Unit collects the funds from the Commission and proceeds with the payments to the Consortium Members. For this purpose, the Coordinator Unit is composed of 1.5 professionals and 3.5 support staff. The Programme Management Unit will be hosted by IPP in Garching. All related costs for providing the required infrastructures that are incurred for hosting these Units (Host support) will be reimbursed to IPP and CCFE respectively. In addition to the purchase of goods and equipment as well as accommodation for the Programme Management Unit (for the 2 sites), the related costs will cover in particular: - The cost relating to scientific publications including the costs for publication of articles in journals and those relating to the IOP database. - The cost for the logistic linked to the experimental campaigns at JET and the other common facilities. - The costs relating to Public Relations - The costs for EIROforum activities - The costs incurred in relation with the International collaborations. Management costs up to 2.5% of the EC contribution (or up to 30k€ if 2.5% of the EC contribution is less than 30k€) can be reimbursed to each Member every year. These costs will have to be justified as personnel costs and other direct costs in line with the Funding Rules of the Consortium to cover management and administrative staff working in support to the work packages, including the participation to the meetings related with the governance of the Consortium. Deliverables: The Programme Management Unit and the Coordinator Unit will have to provide an annual report on the scientific and technical activities as well as a financial statement. Deliverables See table 3.1c
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3.7 Technology Transfer
26 Technology Transfer (WPTT) Objectives In the coming decades the development of fusion will progressively evolve from a science-driven, lab- based exercise to an industry-driven and technology-driven program. During Horizon 2020 this process has started already in key areas such as material development and efficient production of electricity. Therefore, industry will be involved at all levels, from project leaders of relevant work packages, secondees to the PMU, and expert advisors during all reviews of the progress being made in the individual projects and in the programme in general. This exchange of know-how with industry is primarily aimed at ensuring that internal work practices are aligned to industrial standards and that designs take into account requirements of industrial production. Industry will become aware of all technical aspects of fusion that are relevant for its commercial use, which will guarantee a smooth transition to commercial use of fusion power Henceforth, this will be called “Involvement of industry/Transition process” to ensure easy transition. Another aspect of Technology Transfer is the expectation of the financing authorities and the public that research shall bring a return of investment. The transition process to industry is clearly related to technological questions and will therefore need a direct tie to those Work Packages where the technical tasks are implemented. As these Work Packages are mainly grouped within the Fusion Technology part of EUROfusion the management of the transition process has to be a programmatic goal of all these Work Packages. These issues will therefore be managed within each Work Package under implementation of the agreed industrial strategy. Distinct from that is the return-on-investment aspect of Technology Transfer, which could in principle be related to all Work Packages as IP that may be interesting for licensing could in principle emanate from each research field. In addition, it has to be taken into account that all IP generated within EUROfusion will belong to the parties generating it. Therefore, the effort of transferring the IP under licenses can only be seen as a “service” for participating Beneficiaries. THERE SHOULD BE MUCH MORE ON SPIN-OFFS ETC: - THIS IS WHAT IS MEAT BY TECHNOLOGY TRANSFER ! Description of work Following the completion of the FUTTA and FUTTA2 projects, a follow up project FUTTA3 will be launched with the continuation of a consortium of fusion technology transfer brokers setup during FUTTA and FUTTA2 as the main objective. Although the ultimate aim is the establishment of a Technology Transfer Project Office (TTPO) for EURATOM activities, it is proposed to continue the Technology Transfer activities in a similar way during the initial phase of the Horizon Europe programme. The programme will be established in close collaboration with F4E and making use of a wider network of brokers. After the completion of the FUTTA3 project, when EUROfusion has acquired sufficient expertise in this area, a decision will be taken on how to proceed with the activities taking in consideration the outcome of the FUTTA3 project. It might be considered that EUROfusion sets up its own TTPO; it might also be that this is jointly done with F4E.
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Deliverables
ID R&D Deliverables Date Assess the Technology Transfer Activities Programme 2021-22 2022 Implement the Technology Transfer Activities Programme 2023-2025 2022 Report on Technology Transfer Activities implemented in 2021 2021 Report on Technology Transfer Activities implemented in 2022 2022 Report on Technology Transfer Activities implemented in 2023 2023 Report on Technology Transfer Activities implemented in 2024 2024 Report on Technology Transfer Activities implemented in 2025 2025
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3.8 International Collaborations Coordination (INCO) The EU Fusion roadmap articulates a strategy in which ITER is a key facility to provide the first technical demonstration of large-scale fusion power production. With ITER under construction and its first phase of operation foreseen to start at the end of 2025, a significant fraction of the programmatic actions within the next decade is set out to target the provision of the European contribution to the finalization of its construction, together with the preparation for its operation and successful joint exploitation. While the construction is under the remit of F4E, it will significantly benefit from supportive research conducted under EUROfusion as described in other chapters. As for the preparation of ITER operation and exploitation, it is expected that EUROfusion will be significantly involved. This lays out the ground for a pivotal engagement with both the ITER IO and its parties, required to ensure European programmatic interests are given an appropriately ample consideration. Although there is no WP for International Collaborations, the activity relates to several Deliverables and Milestones which are to be reported by the PM. Several other related Deliverables and Milestones are under the relevant WPs. International Collaborations are coordinated by a Senior Manager working directly under the authority of the Programme Manager. Strategy and Objectives The top-level objectives of INCO activities are twofold: To contribute to closing programmatic gaps identified in the implementation of the fusion Roadmap in the period 2021-2027 through targeted engagements with third parties able to provide access to the expertise, facilities or knowledge base sought for; To contribute to fulfilling EU obligations towards third parties derived from EURATOM bilateral and multi-lateral collaboration agreements, in particular the ITER and the Broader Approach (BA) Agreements, while ensuring adequate return for the EU programme. In addition to a strong support provided to the ITER project, the INCO strategy will be mainly guided by the necessity of closure of identified gaps in the implementation of the fusion Roadmap, among which the following provide a good representation as of today: - ITER operating regimes: Shattered Pellet Injection (SPI)-based disruption mitigation (ITER, US and KO) - ITER and DEMO operating regimes: long pulse tokamak operation (JA: JT-60SA, CN: EAST, KO: KSTAR) - Burning plasma physics for ITER and DEMO (US: DIII-D) - DEMO operating regimes: negative triangularity and no-ELM operation (US: DIII-D) - DEMO materials and licensing: DONES Neutron Source supporting technologies (BA, JA, possibly RF) - DEMO materials and licensing: Structural and Functional Materials irradiation in complement to EU reactors (RF, US) - DEMO Breeding Blanket: Liquid Metal technologies, Li-Pb test facilities (RF, JA) - DEMO Fuel Cycle optimisation: pellet injection (RF), advanced pumping technologies (RF), tritium permeation and tritium handling (US) - Fusion Safety: DEMO licensing (BA), safety code development (US) - DEMO Nuclear Instrumentation (US) - NO MENTION OF HTS ??
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The outcome of these DEMO related collaborative activities is expected to bring significant contributions to the DEMO design activities. They will be complemented by research conducted under multi-lateral frameworks, in particular under the IEA-TCPs. The technical work will be conducted under the relevant EUROfusion WPs. More technical details are provided below. Another key strategic guideline for INCO in support to ITER will be the continuation of the ITPA framework: EUROfusion shall be instrumental in keeping Europe as a key player role in the coordination at world level of the physics contributions to ITER operation and scientific exploitation.
Description of work Programmatic context impacting the approach to international collaboration
Existing and new experimental facilities in Europe are well suited to address some of the physics, design and engineering issues at hand and will therefore be natural homes for the implementation of mutually beneficial collaborations with third parties. This is, in particular, true for (i) JET with a possible DT operation in 2023 or the extension of the SPI-based disruption mitigation experiments beyond 2020, (ii) the planned DTT device in Italy with dedicated capabilities to address the quest for an adequate divertor solution for DEMO, and (iii) the MST devices that will play a key role in addressing ITER and DEMO physics issues (including DEMO scenarios) as well as assisting in finding solutions to plasma exhaust. While JET will be most likely phased out by the end of 2024, new facilities are scheduled to become operational in the countries of the ITER Parties with the potential to significantly enrich the European programme. A prominent role will be played by the JT-60SA superconducting tokamak in Japan, which has been jointly built with Europe. JT-60SA will in particular provide the capability for accessing and investigating long-pulse plasma operation in preparation for ITER. EUROfusion is gearing towards playing a key role in the exploitation of this device. Other non-European tokamaks could also offer interesting capabilities that could be considered in order to fill identified programmatic gaps in the realisation of the Roadmap. As a consequence of the recent decision on ITER to reduce the number of ports that will accommodate test tritium breeding blanket modules (TBMs), Europe is bound to collaborate with one (or more) of the ITER Parties for the development, procurement and installation of one if not both of its TBM concepts. This will be a process with significant implications for the development of tritium breeding blanket solutions for the EU DEMO. With ITER under construction, the worldwide magnetic fusion programme is in a transition with an increasing focus on the preparation for the production of fusion energy on an industrial, power plant scale. Hence, similarly to Europe’s approach with its DEMO programme, many ITER Parties are developing programme plans and initiating new R&D activities targeting a demonstration of fusion energy’s readiness for commercialization. This is in particular the case for China, Japan, South Korea and the Russian Federation. For Europe, this opens new avenue for mutually beneficial collaborations in areas where large-scale efforts are required such as the development and qualification of materials in compliance with regulatory requirements, safety, licensing and proliferation resistance. In this context, the implementation of the IFMIF-DONES neutron irradiation facility in Europe is expected to be a key platform for collaborative activities at international level. The start of Phase II of the Broader Approach agreement between Europe and Japan provides the framework for continuing or extending a number of collaborative activities targeting DEMO, in addition to the joint operation and exploitation of JT-60SA.
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The foreseen review of existing facilities in the EU around 2023 is likely to highlight additional gaps in physics and technology that may only be filled through international collaboration. Finally, the end of Horizon Europe will see a number of gate reviews aiming at down selecting technological solutions for DEMO systems and components. This process will be based on the results of a significant technology R&D programme, for which access to facilities outside the EU is required in order to complement European technical capabilities.
High-level guidelines for international collaboration Four high-level guidelines will shape the implementation of international collaborations: well-defined frameworks, mutual benefit, programmatic driving and a careful Intellectual Property Right (IPR) policy.
All international collaborative activities must be implemented within well-defined frameworks, as listed below in the next section.
The principle of mutual benefit must, in all cases, be satisfied, not only in a single topical area, but in the global framework of the collaboration with a given partner. Particular attention will have to be paid to the case of third party participation in JET DT experiments.
In general, the approach to international collaboration shall be pro-active and programmatically driven. As a prerequisite, this requires: The identification of programmatic gaps in the EU as a basis for defining collaboration areas and objectives over the duration of the framework programme; An analysis of technical capabilities of partners; Striving for joint coordinated programmes in some key areas at bilateral level if not at multi- lateral level (e.g. materials); Aiming at complementarity in the implementation of technology R&D facilities, rather than duplication.
In the planning, setting up and execution of international collaborative activities due consideration must be given to the issue of intellectual property rights (IPR) in an effort to prevent leakage with no return for the European fusion programme. Hereby, topics under consideration for collaboration must be vetted against the list derived from the so-called “traffic light” system (green, amber, red) used for sensitivity classification with respect to risks associated with IPR. Implementation of international collaborations In the implementation of international collaborative activities, existing well-defined umbrella agreements are to be used (if not already in place, additional/new frameworks will be needed). This means developing the collaborations under: The bilateral agreements between Euratom and various relevant governments of relevance in the field of fusion energy research (China, Japan, Russian Federation, USA, etc.) and reinforcing programmatic coordination when applicable; The ITER Agreement (under F4E coordination for the European contribution) for the support to ITER R&D and the preparation of ITER scientific exploitation; The Broader Approach agreement (in close collaboration with F4E); The International Energy Agency’s multilateral agreements;
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The International Tokamak Physics Activities agreement. The detailed implementation of the collaborations is to be defined in specific agreements under the higher-level agreements, which spell out objectives, deliverables, milestones, timescales, resources and involvement of each partner. Only for more “academic” type of collaborations may lighter procedures be privileged. A data base of all the bi-lateral collaborations of the Beneficiaries will be maintained and regularly updated as an effective management tool for ensuring the overall coherence of the INCO strategy. Specific provisions within the Consortium will include 100% funding for: Materials irradiation campaigns outside the EU19; International missions of experts from Consortium members in the context of agreed and approved collaborative activities within the various Work Packages; Agreed and established international PhD programmes, in particular targeting the support of the exploitation of JT60-SA; EUROfusion Research Grants and EUROfusion Engineering Grants if implemented in the context of international collaboration. A new criterion “involvement in an international collaboration” is proposed to be added in the evaluation of the EEGs and ERGs20. A number of specific implementation issues requiring a timely resolution include, in particular: The preparation, in close cooperation with F4E, of the European participation scheme in ITER and its agreement with ITER IO; The organisation, in close cooperation with F4E and QST, of the participation of international partners in JT60-SA; The implementation of a new scheme called Early Carrier International Grants (ECIG) setting an international grant scheme for missions with medium duration (3-6 months) for early carrier European scientists with up to 10 years experience after PhD. The scheme should be based on competitive calls and recipients selected upon quality of proposal and scientific excellence of proponent as well as international partner team(s). Budget for missions under international collaboration will be allocated to the respective Work Packages and the responsibility for their implementation and reporting transferred to the corresponding Project / Task Force Leaders. Main topics identified for collaboration with the international partners Based on analyses of programmatic gaps conducted throughout all Work Packages, the following topics have been identified as potentially with the highest impact on the Consortium’s programme during Horizon Europe, if addressed with the indicated third parties in the context of international collaboration (this list will be regularly updated during the course of Horizon Europe).
19 It should be noted that neutron irradiations on materials test reactors are complex endeavours that require substantial collaboration with the party conducting the irradiation campaigns. This provision is meant to allow for full payment of material irradiation on non-EU reactors. However, in some cases, irradiation campaigns or part of campaigns might be trade-off against other activities offered by Europe 20 Although not as a compulsory criterion but as a way to gain “bonus” points in the final mark of an ERG or EEG proposal Page 138 of 143
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Third Party Topic
China Long pulse tokamak operation Physics & operational assessment of alternative divertor geometries, in particular on HL-2M, as candidate solutions for DEMO Physics & operational assessment of tokamak with negative triangularity and related naturally no ELMs scenario as candidate for DEMO Work on complementary DEMO/CFETR technology R&D devices Design of CFETR DTT/CFETR collaboration (ICRH, NB, coils, divertor)
Japan Commissioning, operation and physics exploitation of in JT60-SA under the BA agreement R&D on IFMIF – DONES / A-FNS related technologies both within the BA agreement and the bilateral agreement High Performance Computing both within the BA agreement and the bilateral agreement Stellerator / heliotron physics and operation (LHD-W-7X collaboration) WCLL breeding blanket design R&D for materials corrosion data base, neutron irradiation experiments for breeding materials, tritium technology and tritium permeation barriers
ITER IO Construction, commissioning and exploitation of a second SPI on JET Development of IMAS and implementation on EUROfusion experiments Preparation of operation for first plasma and non-nuclear phase Contribution to the exploitation of the NBTF
Republic of SPI-based disruption mitigation experiments Korea Integrated modelling HCPB Test Blanket System on ITER
Russian Diagnostics (neutrons, gammas, NPA etc.), Federation Modelling (SOLPS-ITER, impact of transients on PFCs, irradiation damage, etc) Fuel cycle (pellet injection, advanced pumping technologies, possibly T technologies) Materials physics, including experimental investigation of materials damage during thermal transients Neutron irradiation of structural, high heat flux (BOR-60 reactor) and functional (IVV-2M reactor) materials
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Version 6 May 2020
Liquid metals technologies and testing for breeding blankets and divertor applications
USA SPI-based disruption mitigation experiments on JET and construction, commissioning and exploitation of a second SPI on JET (in case of an extension of JET beyond 2020) and comparison with DIII-D Physics assessment of QH-mode; I-mode, negative triangularity and DN as contribution to DEMO Physics basis, in particular on DIII-D DEMO safety and licensing: Fusion safety code development (Melcore- TMAP); safety assessments; waste management; Risk Assessment and failure rate data collection; design criteria for In-Vessel Components including a Multiscale-Multiphysics design frameworks; safety assessments in support of DEMO design work; waste management strategies Technology R&D: neutron irradiation in High Flux Isotope Reactor (HFIR, ORNL); tritium handling in coolant streams and other hazardous materials (SRNL); tritium permeation through PFCs and blanket/structural components; MHD modelling in liquid metal for blanket applications; nuclear instrumentation; cryogenic materials Burning plasma physics …..
Deliverables
Deliverables Table End Date Defined scheme for EU participation in ITER exploitation 2022 Report on PhD programme on JT-60SA 2025 Report on assessment of INCO contribution to tackling Roadmap-related 2026 R&D issues
Milestones Key Milestones related to INCO: - Start of the new ECIG scheme (2021) - Finalisation of the scheme for EU participation in ITER exploitation (2022) - Start of PhD programme on JT-60SA (2022)
There are several INCO related key Milestones that will be executed under other Work Packages: - First JT60-SA experimental campaign (2021) - Completion of first material irradiation campaigns conducted on foreign Partners reactors (2023) - Double-SPI experiments on JET (if JET is used beyond 2020)
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3.9 Industrial Involvement
The nature of engagement between industry and fusion labs will evolve according to the phase of the programme to make best use of industry competencies at the appropriate stages. This is a progressive process with industry working in partnership with research organisations, possibly in the form of consortia. Therefore, a ‘streamed’ industry engagement strategy is envisaged, that seeks to make the most effective utilisation of industry skills & experience during each development phase. This strategy comprises four streams, where each defines classes of industry engagement as summarised below: Stream 1: Systems engineering/project and programme support & development/technology evaluation Stream 2: Technology and materials joint development R&D projects Stream 3: Specialist ‘design’ and ‘project management’ close support Stream 4: Construction and test of 'DEMO Large Projects' The streams run concurrently, with start and end points related to, though not coincident with DEMO phase boundaries. Phase 1: Pre Conceptual Design (2014-2020) - as part of Horizon 2020 During the pre-conceptual design phase the DEMO requirements were established through thorough analysis of the DEMO context and engagement with industry stakeholders. Design points were investigated and evaluated, and feasibility issues explored to identify the most promising concepts. The programmatic and technical frameworks required to manage and coordinate the design activities from pre-concept onwards were established and implemented with industry support. Industry involvement during this phase was implemented in streams 1 & 2.
Figure 5: Overview of Industry Engagement Streams mapped to DEMO design development phases
Phase 2: Conceptual Design (2020 -2027) – as part of Horizon Europe A review of the DEMO concept definition should be made, involving the relevant stakeholders. This review should involve utilities and system engineering companies as for the Gen IV fission programme to ensure that before launching engineering design activities, there is full acceptance of the proposal by these stakeholders. The implementation of this phase will require the use of individual contracts for industrial experts to work within the DEMO Design Team in the specific areas where industrial management practice, knowledge and technical practices are required. The organisation or project team should specifically include a systems engineering group. In addition, in order to broaden the industrial landscape and prepare for strong consortia in the Engineering Design (ED), the skills and knowledge of universities, research institutes and industry should be tapped to provide innovative solutions to difficult problems. 301
This phase is characterised by the continuation of streams 1 & 2, and the progressive implementation of stream 3. The key activities where industry involvement is foreseen are described below: Continuation of project management and technical management support, with particular emphasis on implementation of industrial project and knowledge management processes, cost estimation, schedule development and risk management. Definition (together with the research laboratories) of the priorities in the technology development; and participation in DEMO-specific technology and materials R&D, especially in high-impact areas. Demonstration of critical enabling technologies. Concept engineering design participation in specific areas of expertise (e.g. Balance of Plant, Blanket, Remote Handling). Support of technical reviews of the major systems. Support in development of Safety & Operational aspects, including safety engineering & licensing support, and development of the maintenance and operational strategy. Developments of codes and standards to support the ED. Review of DEMO integrated plant concept design, and major systems by stakeholders for full acceptance of the proposition. In addition, some participation of industrial experts in the ITER commissioning, operation and exploitation (together with the IO members, scientists and engineers from the fusion labs) is envisaged in order to gain sufficient expertise in the operation of nuclear fusion reactors and to gather plasma and fusion technology know-how to be used for DEMO design and engineering activities. Involvement of industry in the material development (Mission 3) Involvement of industry in Mission 3 takes place in two very different ways. On the one side, materials development must include strong emphasis on the industrialisation of the candidate materials, including issues of industrial-scale production and joining techniques, with a strong participation, as a full partner, of industries responsible for fabrication, qualification, testing and components manufacturing according to codes and standards. Major industrial organisations could provide advice from Gen IV programmes and facilitate the interaction with the broader supply chain. An effort should be made on seeking synergies with other community-funded advanced materials programmes. The experience of the Research Fund for Coal and Steel has shown that if grants with substantial Community share are available there is a substantial direct involvement of industries. Nuclear industry materials groups are also heavily involved in the SNETP (Sustainable Nuclear Energy Technology Platform)21. The possibility for joint bids with industry for RFCS grants has already been explored at the end of the EFDA period and will be actively pursued by the Consortium. On the other side, the early construction of DEMO requires the accelerated construction of a neutron irradiation plant to test fusion relevant materials. This plant will initially have reduced specifications in terms of accumulated damage of the irradiated materials (20-50 dpa instead of 150 dpa). In this work programme the assumption is that the construction of this facility will be started in the early 20´s. In order to be able to implement this approach, industry must have a very relevant role in the related engineering design activities as well as in the project organization. The role of the industry should also increase as the start of this project nears. During Horizon Europe, as was the case during Horizon 2020, partnerships between research laboratories and industries should be facilitated by the EUROfusion Consortium by supporting joint programmes. Resources for R&D activities could be made available also from other Community
21 One of its main task forces, ESNII (European Sustainable Nuclear Industry Initiative), is supporting projects like ASTRID (Advanced Sodium Technological Reactor for Industrial Demonstration 600 MWe), MYRRHA (Multipurpose hYbrid Research Reactor for High tech Applications) and ALLEGRO (gas Fast Reactor) accounting for a ~10B€ budget. 302
programmes. These joint programmes could naturally evolve in consortia between industry and laboratories in the DEMO engineering design phase. Industry Framework Council Regulation (Euratom) 2018/1563 of 15 October 2018 on the Research and Training Programme of the European Atomic Energy Community provides funding for actions in nuclear research, complementing the Horizon Europe framework programme. The technical specification defined by the European Commission forms the basis of the Multiple Service Framework Contract “Supply of expert industrial competences for the conceptual design activities of the European DEMO and the IFMIF-DONES”. The objective of the framework is to obtain an assessment based on industry-best practice of the nuclear fusion Power Plant Physics and Technology system architecture, overall configuration and system engineering processes, with a focus on design and technology options and feasibility, manufacturing options as well as risk identification, evaluation and mitigation. An evaluation of the impact on cost for the suggested solutions will also be included. The scope of the framework covers a range of technology aspects related to nuclear fusion engineering. The following topical areas are identified for the time being to form the basis of the framework: Project and Plant industry best practices Safety Plant and Component design and lifecycle Plant control system and operation It should be noted that given the nuclear nature of DEMO and its impact on social acceptance, nuclear safety compliance assessments (and demonstration, where required) are included in the scope to cover the plant lifecycle. Participation in DEMO Conceptual Design. This should be done through the delegation of key industrial personnel to the project team with appropriate support from their parent organisation and could be managed either directly by the EUROfusion consortium or by the laboratories involved in the programme. Industrial expertise will be integrated at all levels in the review process. Knowledge management system. Such a system should be set up to conserve both explicit (engineering and design data, integration procedures, operations, test procedures and test results, etc.) and implicit knowledge (knowledge of individuals) acquired during the development and operation of ITER for future generations of engineers and operators. To preserve the implicit knowledge entails setting up a systematic, structured approach to transfer the know-how of retiring experts to their successors; a lessons-learned management system should be set up to capture lessons gained from mistakes made during system engineering, design, integration, test and operations, together with a best-practice conservation system which captures "tips and tricks" gained by experience. Legal aspects. An area that requires specific attention is that of legal aspects of know-how management (Intellectual Property Rights, patents, non-discloser technologies). This should be discussed well in advance of the start of the DEMO Engineering Design Phase to facilitate the involvement of industry. The period between the end of the ITER construction and the start of the DEMO Engineering Design Phase should be used to review the lessons learned from ITER construction and the results of the DEMO CD phase in order to define the best implementation tools for the DEMO ED phase.
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