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Fusion Nuclear Science Facility, Moovaoon and the Program To Improved modelsRequired for radiating edge-plasmasfunctionality for ACT-1 and R&D for breeder blanket 1. Kinetic Monte Carlosystems neutrals for pumping 2. Multi-charge-state impurities for radiation M.E. Rensink and T.D. Rognlien ARIESPresented Project Meeting by Neil Morley & Mohamed Abdou, UCLA SanWith Diego, contributions CA from the FNST community Jan. 22-23, 2013 Fusion Fusion Nuclear Science Pathways Assessment Energy Gaithersburg, MD, December 3, 2010 Systems Studies This work was performed under the auspices of the U.S. Department of Energy by Lawrence Livermore National Security, LLC, Lawrence Livermore National Laboratory under Contract DE-AC52-07NA27344. LLNL-PRES-612712 1 Fusion Nuclear Science Facility, Mo3vaon and the Program to Develop a Basis for Power Plants C. E. Kessel, PPPL J. Blanchard, A. Davis, L. El-Geubaly, L. Garrison, N. Ghoniem, P. Humrickhouse, Y. Huang, Y. Katoh, A. Khodak, E. MarrioL, S. Malang, N. Morley, G. H. Neilson, J. Rapp, M. Rensink, T. Rognlien, A. Rowcliffe, S. Smolentsev, L. Snead, M. Tillack, P. Titus, L. Waganer, G. Wallace, S. Wukitch, A. Ying, K. Young, and Y. Zhai 4th IAEA DEMO Program Workshop, Karlsruhe, Germany, November 15-18, 2016 The Fusion Energy Systems Studies Team is Examining the Fusion Nuclear Science Facility What does an FNSF have to accomplish? How do we measure the FNSF progress for fusion development? How does the FNSF accomplish its mission? What is the pre-requisite R&D needed for an FNSF? What does the FNSF require from our program to succeed? How does an FNSF fit in the larger fusion development program? What cri3cal insights about this facility can be uncovered, impacts of assump3ons, technical choices and philosophies,…? The FNSF is the First Step in a Two-Step Pathway to Commercial Fusion Power Plants First strongly Demonstrate roune burning plasma power plant operaons No Power ITER FNSF DEMO technical Plant gaps Max neutron 3 dpa 37-74 dpa 100-150 dpa 150+ dpa damage Max plasma 500-3000s 1-15 days 15-365 days 365+ days pulse TBR ~ 0 ~ 1.0 1.05+ 1.05 Tblanket, Tcool,exit 285C, 150C 550C, 650C 550C, 650C 550C, 650C 316SS, CuCrZr, RAFM, PbLi, He, SiC-c, Materials Borated-RAFM, W, Be, W, H2O, SS304, SS430 baini3c steel The FNSF is the First Step in a Two-Step Pathway to Commercial Fusion Power Plants Fusion nuclear break-in Rou3ne electricity produc3on min ITER FNSF mod DEMO Power Plant max Largely the same To have no star3ng point based on technical gaps proposed facili3es from DEMO to AddiMonal R&D on DEMO a PP What is a Possible Time-Frame and Where Does the FNSF Reside* This schedule is used for illustraon 2020 2030 2040 2050 2060 ITER Non-DT, TBM DT, TBM FNSF He/DD DT Present and near term confinement devices, short pulse US DEMO à to long pulse Pre-FNSF R&D Parallel FNSF R&D and pre-DEMO R&D FNSF design DEMO design Pre-C Conc Prelim Final Pre-C Conc Prelim Final FNSF DEMO construcon construcon * US does not presently have a commitment to design and construct the FNSF or DEMO The FNSF IS NOT a Power Plant BUT, its program is designed to establish the “database” for DEMO and subsequent power plants…it combines research, development, and demonstraons The FNSF has a mul3-faceted purpose to break-in to the fusion nuclear regime 1) Perform the materials research within the nuclear fusion in-service environment 2) Establish the operaon of fusion core components (made of these materials) over the prototypical range of environmental parameters (T, pressure, hydrogen, etc.) with fusion neutrons 3) Establish the operaon of mul3ple subsystems/func3ons cri3cal to fusion, such as tri3um breeding, recovery, control, fueling, exhaust, and storage…..others include power handling, maintenance, measurements, fusion enabling technologies, etc. 4) Establish the ultra-long plasma pulses, with high performance, sustained by a range of plasma enabling technologies Power Plant Relevance is cri3cal to the FNSF, to prepare for future device’s operang regimes and to provide a comprehensive experiment on the fusion core and ex-core The pre-FNSF Component Development and Phased Operaon on the FNSF are Essen3al for Success On the FNSF we will have some failures, but the presence of constant failures are incompable with the plasma-vacuum systems and the need for radioac3ve materials remote handling We will use a high level of pre-qualificaon of materials and components We will test all materials in the fusion core up to the an3cipated dpa level before operang to that dpa level on the FNSF, with fission and fusion relevant neutron exposures We will test the most integrated prototype possible of blanket, divertor, and launcher components before installaon, in a non-nuclear integrated facility On the FNSF, the phases rampup the operang parameters slowly to provide monitoring The plasma duraons, duty cycles, dpa’s, and operang temperatures are advanced through the 1 DD, and 5 DT program phases Inspec3ons and autopsy of components is used to monitor evolu3on of materials, requiring highly efficient hot cell turn-around, during any given phase and at the end of a phase Test blanket modules will be used for a “look forward”, engineering tes3ng, backup blanket concepts, and material sample tes3ng Missions of the FNSF, Using Metrics to Show How Much Progress We Are Making to Address Them Strongly advance fusion neutron exposure of fusion core (ex-core) components toward power plant levels U3lize and advance power plant relevant materials Operate in power plant relevant fusion core environment (T, p, v, B, etc.) Produce tri3um in required quan33es, compensang consump3on, decay and losses Extract, process, inject, and exhaust tri3um in manner that meets all safety criteria, and high level of predic3on, control and accountancy Rou3nely operate very long pulse plasmas, longer or long enough to access required phenomena, with sufficient plasma performance Advance and demonstrate enabling technologies Demonstrate safe and environmentally friendly plant operaons (tri3um leakage, hot cell operaons, radioac3ve material handling, etc.) Develop power plant relevant subsystems for robust and high efficiency operaons Advance toward high availability, reliability, efficient maintenance operaons, etc. Sampling of Metrics for Some Missions ITER FNSF DEMO Power Plant ARIES-ACT1/2 1. Strongly advance the fusion neutron exposure….. Life of plant peak 0.3 12.6 88 FW fluence, MW- yr/m2 (life of plant) (8.4 FPY) (40 FPY) Peak FW fluence 0.3 0.7, 1.9, 2.6, 3.7, 15-20 to replace blanket, 7.4 MW-yr/m2 (dpa) (replacements) (3) (7, 19, 27, 37, 74) (150-200) (0) (5) (4-6) Peak FW neutron 0.76 1.75 2.2 wall load, MW/m2 (average) (0.56) (1.18) (1.46) 4. Produce tritium in quantities that….. TBR - total 1.06* 1.05 Tritium produced 0.004 10.7 101-146 per year, kg Li-6 enrichment 90% 40% OB FW hole/loss 7-9% 4% fraction 6. Routinely operate very long plasma durations…. Plasma on-time 5% 35% 85% per year (ave) Plasma pulse 500-3000 1.2x106 2.7x107 duration, s Plasma duty cycle 25% 95% 100% βN H98 / q95 0.6 0.4 0.4-2.1 Q 5-10 4-6 25-48 fBS 0.25-0.5 0.52 0.77-0.91 Pcore,rad / (Palpha + 0.27 0.24 0.28-0.46 Paux) Pdiv,rad / PSOL 0.7 0.75-1.0 0.75-1.0 *depending on assumed H/CD systems Why Pursue a Smaller First Step, like the FNSF? Untested regime of fusion neutrons on mul3-materials under mul3-factor environment Fission experience with materials (learned from PWR and breeder development programs) - Extreme sensi3vity of swelling with temperature - Impacts of irradiaon dose rate increased hardening and threshold for swelling - Impacts of smaller cons3tuents ~ 0.5 wt% can lead to posi3ve and negave effects - Surface condi3ons, welds, and metallurgic variability provided wide variaons in irradiaon behavior - Incubaon periods that delay the emergence of a phenomena - Simultaneous mul3ple variable gradients (neutron fluence, temperature, stress) on crack behavior - Radiaon induced segregaon, precipitaon, modified thermal precipitaon - ….... Goal is to establish the actual fusion in-service material and scien3fic/ engineering database on all components in the fusion neutron environment and in the overall environment before moving to larger size and electricity produc3on This is NOT the same database that we used to pursue the FNSF, it replaces/augments it The smaller intermediate step (FNSF) on a path to power plants à what comes before FNSF Neutron irradiaon of individual materials in 1) fusion relevant neutron source, 2) fission reactor and doping, 3) ion bombardment Prototypical parameters & Integrated blanket component tes3ng & Trium science integraon ITER TBM progress (weak nuclear) (LiPb) Liquid metal science Magnets Helium cooling Diagnos3cs Integrated diagnos3c tes3ng Enabling technologies Fueling/exhaust Heat exchanger Trium processing Heang & current drive Integrated launcher/guide tes3ng …... Plasma facing components/plasma material interac3ons in 1) tokamaks, 2) linear plasma devices, 3) offline (e.g. HHF, liquid metal) integrated PFC tes3ng Plasma development in 1) short pulse tokamaks, 2) long pulse tokamaks (EAST, KSTAR, JT-60SA), 3) ITER The smaller intermediate step (FNSF) Temperature. Deg C on a path to power plants à what is 543 C unique about the FNSF The environment in the FNSF will not have been seen before, the combinaon of fusion neutrons and the mul3-physics non-nuclear environment plasma 350 C Helium production (appm) for DCLL Blanket 100 dpa at plasma facing side LiPb, ~3MPa example 94 MPa 15001000500 25 plasma appmHe 0.6 MPa A M 100 8060 40 20 He, 8 MPa Von Mises stress S A PL dpa Y.
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