SMR Technology Development in Russia and Capacity Building Supports for Embarking Countries

“Rosatom Technical Academy” (Rosatom Tech)

IAEA Technical Meeting on Technology Assessment of Small Modular Reactors for Near Term Deployment 2 – 5 October 2017 Tunis, Tunisia

Vladimir Artisiuk

1. Nuclear technology in Russia in a nut-shell 2. New generation of Russian SMRs 3. HRD issues (NNP personnel)

Number of Power ~ 18,6 % of total electricity generation Units: 35 - EGP-6 Unit SMRs - BN Unit Total Installed Kola - VVER-1000 Unit - VVER-440 Unit Bilibino Capacity: 28.3 - RBMK Unit GW Leningrad - VVER-1200 Unit 4 x12 MWt Smolensk Kalinin Startup- 2- 1974 Kursk 2- 1976 Novovoronezh

Rostov Balakovo Beloyarsk

Reactor Types

http://www.rosenergoatom.ru/stations_projects/russian_nuclear/

© Rosatom Tech 4 Nuclear Reactors for Submarines (predecessors of commercial PWR –reactors) USS Nautilus - 1955 K-3 "Leninskiy Komsomol“ - 1958 Fuel – Zr + uranium Fuel – uranium 235U≈21% 235U≈93% Power output ≈ 2 x 70 MW Power output ≈ 10 MW Core Lifetime: 1440 hours Core Lifetime ≈ 900 hours

S2W (Submarine Thermal Reactor Mark II / STR MK II) ≈ 210 nuclear submarines (220 reactors) ≈ 250 nuclear submarines (450 reactors) E. Seeger, Underway on Nuclear Power: 50th Anniversary of U.S.S. Nautilus © Rosatom Tech 5 (Faircount Publication, 2004) Nuclear propulsions. Icebreakers

Ship Name Startup Shut down Reactor Type Power (MWt)

Lenin 1959 1989 OK-150 replaced OK-900 90

Arktika 1975 2008 ОК-900A 171

Sibir 1977 1992 ОК-900A 171 Rossiya 1985 2013 ОК-900A 171 Sevmorput 1988 - KLT-40 135 Taymyr 1989 - KLT-40M 171 Vaygach 1990 - KLT-40M 171

Sovetskiy Soyuz 1990 2010 OK-900A 171 Yamal 1993 - OK-900A 171 50 Let Pobedy 2007 - OK-900A 171

http://www.okbm.nnov.ru/reactors © Rosatom Tech 6 WWER Technology – History of Implementation

 AES-2006 (WWER- 1200, 60 years lifetime, 90% capacity factor)

 WWER-TOI (WWER-1300, Typical Optimized Informative- advanced project)

 AES-91 (WWER- 1000)

 AES-92 (WWER- 1000) WEST: PWR Russia : WWER (VVER) Water Cooled Water Moderated Energy Reactor © Rosatom Tech 7 Challenge of Growing Training Demands. Russian Case: VVER-NPP Overseas

Experience Plans

1200 Bangladesh 1424 1000 Egypt 2030 Turkey 1917 800 Iran 1631 Finland 450 600 Hungary 42* * instructors only Russia 35000 Iran 1236 400 Czech&Slov 952 Bulgaria 917 200 Hungary 869 Cuba 707

China 454 Finland 360 0 Belarus 264 India 182 4 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 Germany 143 20172018 2019 2020 2021 2022 2023 2024 2025 2026 2027 2028

The first world reactor of the Generation III+ (Unit 1 of the Novovoronezh II NPP) connected to the grid

BN-800 (Sodium Fast Reactor, Unit#4 Beloyarsk NPP) started operating at 100% power

JSC TVEL and Vattenfall Nuclear Fuel AB (Sweden) signed a contract for the supply of TVS-K fuel assemblies for the Ringhals NPP

Irradiation test of the REMIX fuel started at Balakovo NPP (VVER-1000) REMIX is the non-separated mixture of U and Pu from LWR SNF reprocessing, with the addition of enriched uranium

Capacity Lifetime FC Construction Title Designer Type Status MW(el) (years) (months) time SMR at the operational stage Daily regime of maneuvering in the Bilibino NPP UralTEP EGR 48 15 4 40 range of 5-100% SMR at the construction stage Academic- JSC Commissioning Lomonosov FNPP VVER 70 40 36 Africantov (start –up 2019) (КLT-40S) SMR projects with electrical capacity 100KW-1MW (e)

TVS GT IPPE LBFR 0.05/1/10 30 360 Construction 4-6 Concept

Project-3 High project elaboration Vitiaz NIKIET VVER 1 30 84 Construction - 3

PT definition of SVBR-MGR IPPE LBFR 1/1.5 360 terms- 1 year Concept SMR projects with electrical capacity 1-20 MW (e)

Project-3 Concept Akkord IPPE VVCR 3/15/30 60 240 Construction - 2

GIDROPRES Project-3 Angstrem LBFR 6 30 72 Draft S Construction - 2

Project-3 30 Engineering development Shelf NIKIET VVER 6 84 Construction - 2

Project-3 Technical proposal Uniterm NIKIET VVER 6.6 60 180 Construction - 2

Capacity Lifetime FC Construction Title Designer Type Status MW(el) (years) (months) time SMR projects with electrical capacity 1-20 MW (e)

PNAEM-8 JSC Africantov 8 180 Project 3.5 Concept

Project-2 ABV-6E JSC Africantov VVER 9 144 Construction Technical proposal 4.5

Iceberg JSC Africantov 16 30 180 Project-3.5 Technical proposal

Project-2 SVIR-10/SVIR-50 GIDROPRESS LBFR 10/50 60 60 Construction Concept 4.5 SMR projects with electrical capacity 20-100 MW (e) Heat Technical and operational Ruta-70 IPPE PT 60 Construction 3 production documentation in IPPE

WWCR-М/ВРК- Project-3 NIKIET VVECR 20/45/100 80 30 Technical proposal 100 Construction 3

Project-3 SVBR-10 GIDROPRESS LBFR 24 60 204 Construction 3 Technical proposal Project-2 RITM-200 JSC Africantov FPU 50 60 120 Construction Manufacturing 4.5 Project-3 NIKA NIKIET VVER 100 60 36 Construction 3 Technical proposal

SVBR-100 GIDROPRESS LBFR 100 60 96 Engineering development finished * S - Static, F - Floating, Sm- Submerged, Т- Transportable © Rosatom Tech 12 SMR Fast Reactors with HLMC – SVBR-100

Experimental Series “Alpha” Reactor NPS class prototype (1963) NPS Pb-Bi rig 27/VT Experimental (1977-1981) (1951) (1958) NPS K-64 (1971) SVBR-100

https://www.iaea.org/NuclearPower/SMR/ Evolution of Lead-Bismuth Fast Reactor Technology • The SVBR-100 is a multipurpose small modular fast reactor lead–bismuth (LBE) cooled, 100 MWel. • SVBR-100 is the Russia's first innovative project in NPP development conducted in the format of public-private partnership – Rosatom opens the doors for international investors in the SVBR-100 reactor project

http://www.rosatom.ru/journalist/smi-about-industry/rosatom-dopuskaet-prikhod-zarubezhnykh-investorov-v- proekt-reaktora-svbr-100/?sphrase_id=62773

Engineering design of the integral 100 MW lead-bismuth The IP-portfolio of "AKME- fast reactor with inherent safety and high engineering" reached about 120 of proliferation resistance features (SVBR- patent applications in 2016. 100) has been completed. http://www.akmeengineering.com/419.html https://www.iaea.org/sites/default/files/16/08/ntr2016.pdf

• BREST-OD-300 is a lead-cooled inherently safet reactor for the NPP Pilot & Demonstration Energy Complex with an on-site fuel cycle.

• The project of BREST-OD-300 incorporates the best technological solutions of the studied fast reactor concepts. Main critical components and equipment (including fuel assemblies with MNUP fuel) have been successfully tested for BREST reactor. http://www.rosatom.ru/en/press-centre/industry-in-media/siberian-chemical-combine- has-successfully-completed-tests-and-post-irradiation-examination-of-its- e/?sphrase_id=62744

http://www.rosatom.ru/journalist/news/atomenergomash-provel-gidroispytaniya- kamery-parogeneratora-dlya-reaktornoy-ustanovki-brest-od-300/?sphrase_id=62745

https://www.riatomsk.ru/article/20170114/rosatom-brest-300-project-in- scp-is-optimized-but-not-frozen/ © Rosatom Tech 15 Achievements for Domestic Consumption: Marine Reactor Plants

Four generations of marine reactor plants

OK-900 KLT-40 OK-150 RITM-200 (OK-900A) (KLT-40M, KLT-40S)

Reactor plant with integral Reactor plant with modular design of steam- Loop-type design design of steam-generating generating unit unit

http://www.okbm.nnov.ru/images/pdf/ritm-200_extended_ru_web.pdf © Rosatom Tech 16 Floating Nuclear Power Plants: Solution for Coastal Areas Power Supply

Akademik Optimized Floating FLOATING Lomonosov Power Unit NUCLEAR POWER (KLT-40S) (RITM-200M) PLANT KEY OPTIMIZATION Capacity (e) 77 MW (2 x 38.5) 100 MW (2 x 50) FIELDS Capacity (th) 300 MW 350 MW

Thermal power . SNF storage unit with electric power 146 Gcal/h 170 Gcal/h removed due to FLOATING NUCLEAR reduced to 58% extended fuel cycle POWER PLANT WITH (10 years) RITM-200M / KLT-40S Length 140 m 112 m POWER REACTORS . Living areas optimized Beam 30 m 25 m . Positioning system is designed to supply Draft 5.6 m 4.5 m (dynamic or berth- connected positioning) electricity, thermal Displacement 21,000 t 12,000 t power, and desalinated . General optimization water to coastal or Fuel Campaign 3-5 years 10 years isolated territories, 40 years 40 years offshore installations, Lifecycle (up to 50 years) (up to 60 years) islands, and Towed or archipelagoes. Mobility Towed self-propelled

On September 1, 2015 in the St. Petersburg branch of ROSATOM- CICE&T started training courses for 17 crewmembers of first Russian Floating NPP. Practical training involves full- scale simulator , which allows simulating all possible operation modes, including emergency. More information:

http://rosatom-cicet.ru/?p=1784

Onshore RITM-200 – based NPP solution

SMALL NUCLEAR POWER PLANT WITH RITM-200

Key NPP design features

TECHNOLOGY RITM-200 2 with the possibility of further Number of modules extension Human resources Fuel supply Thermal capacity > 350 MW(t) training and throughout the Electric capacity > 100 MW(e) Comprehensive development whole lifecycle spent nuclear fuel Average fuel enrichment < 20% and radioactive waste management Fuel campaign 5-7 years solution Operating life 60 years

Capacity factor 98% Engineering Long-term service consulting in NPP and maintenance Construction period 3 - 4 years management and and spare-parts maintenance supply

• Anticipated commissioning date: 2018 • Reactor type: RITM-200 (175 MWt) http://www.okbm.nnov.ru/russian/universalicebreaker http://www.interfax.com/newsinf.asp?pg=2&id=722756

ZIO-Podolsk has completed assembling the integrated reactor vessel of the second of two 175 MWt reactors for the Arktika icebreaker. http://www.world-nuclear-news.org/NN-Russia-completes-second- reactor-vessel-for-Arktika-09051601.html

Reactor plant has been installed on the Arktika icebreaker http://www.rosatom.ru/journalist/smi-about-industry/na-ledokol-arktika-ustanovlen-atomnyy- reaktor/?sphrase_id=66461 © Rosatom Tech 20 HRD issues NNP personnel training in general (the case of VVER) Experience with Floating NPP Support the emerging countries

© Rosatom Tech 21 E&T Path for the Position of Control–Room Operator E&T(in Russia)Path for the Position of Control–Room Operator (in Russia) University Education On-the-job-training University Specialization 5-5,5 yrs 1-5 yrs

«Nuclear Power Plants and Facilities» engineer/specialist NPP

Fields of professional competences: 4 yrs • Management • NPP structure & design • Commissioning & maintenance NPP BS 4 yrs 2 yrs 4 yrs - Bachelor degree 2 yrs - Master degree 5.5 yrs – Specialist BS MS NPP

The specific of Russia is that, compared to western education system, there is a university specialty “Nuclear Power Plants and Facilities”

2.Training of NPP operating personnel 228 VVER NPP Staffing

Job distribution (Russian NPP)

Department Staff Number

Essentials of HRD in Emerging Nuclear Countries

NPP Staffing options (VVER) (1.1) (person/MW)

(0.7)

(0.49) Training in TC of recipient country – up to 900 persons (0.37) Key personnel Training in Russia Personnel for Nuclear Programme (operating personnel, mid-level and  Nuclear Energy Program top managers): Implementing Organization (NEPIO) up to 200 persons per 1 unit – 50 persons up to 300 persons per 2 unit  Regulatory body (RB) – 70 persons  Operating organization (OO) – 150 persons Total: 270 persons/country – training in Russia

Reactor start-up

96 months 60 months 56 months 55 months The beginning Completion of The beginning of The beginning 6 month of the Training the Training full-scope of training in First criticality Centre Centre simulator the Training construction development Centre 15 months Commissioning

-8 -7 -6 -5 -4 -3 -2 -1 0

The beginning of NPP construction

Development of NPP staff recruitment, Commissioning of technical 20 months specifications for manning and admission to training (with the exception of Put full-scope CBS. The beginning self-guided work full-scope simulator) simulator into of EMA creation operation

The integrated development schedule of SMR based on the referential RU

Design Design assignment documentation for SMR development SMR Project with Production and R&D implementation complete supply of Operation pilot SMR components

3 years Construction

6 years

The integrated development schedule of SMR based on the innovative project

Design Design assignment documentation for SMR development SMR Project with R&D implementation Production and Including works supporting fuel complete supply of pilot composition SMR components Operation 7 years Construction

10 years

Staff: 195 (including on-shore)

Staff on board: 70

Number of shifts: 3

Operating Shift: 1 FNPP supervisor 2 Unit Supervisor 2 Reactor operators 2 Turbine Operators To organize Floating NPP personnel training the following was developed: • Operating personnel instructions; • Typical programme of training for Floating NPP personnel for a specific position; • Training materials (more than 200 TMs have been developed including thousands of pages in total); • Lesson plans; • Interactive and 3D models for complex nuclear power facility systems; • Control questions on each topic and test questions for the final certification on each course • A complete set of documents is uploaded on a server with open access for trainees

To practice work in the crew, each employee in training under the leadership of the unit heads performs

• procedure for the use of FNPP primary fire-extinguishing equipment • actions for the use of personal protective equipment for the skin and respiratory system • procedure of using water-fighting equipment • organization and procedure for conducting a radiation safety audit • organization and procedure for decontamination works.

Full scope AS start-up simulator start-up

Training material Training implementation Fuel Development: Training material development: NPP load General courses Systems & Equipment Task Order and Scope of Work Training with the development for use of AS Analytical Simulator (AS) Development of AS

Training start-up Training start-up Workforce Plant Shift Supervisor Reactor hall shift analysis & (14) Unit Shift supervisor (14) Staffing Plan Supervisor (14) Turbine hall shift Commissioning development supervisor (14) personnel Senior reactor operator (14) Senior turbine Personnel training operator (14) schedule & Information System development

“Introduction to Nuclear Power, Physics and Small Modular Reactor Technology” (by G.I. Toshinskiy)

Topics: • Fundamentals of Nuclear Reactor Physics • Nuclear Chain Fission Reaction Fundamentals • The Principle of Nuclear Reactor Operation • Classification of Nuclear Reactors • The Principal Types of Neutron-Nuclear Interaction, Essential for Fission Chain Reaction • Effective Neutron Multiplication Factor in an Infinite Medium • Effective Neutron Multiplication Factor in a Finite Size Reactor • Neutron-Physical Processes Running on in a Reactor during its Operation • Brief Analysis of Nuclear Accidents • Physical Principles of Safety Assurance • Modular Lead-Bismuth Fast Reactors SVBR- 100 in Nuclear Power Industry

Training Course on R&D on design, manufacture and qualification activities for HTGR, Russian Federation, 06 November – 01 December, 2017

Training Course on HTGR/SMR Project Management Russian Federation, 30 October - 03 November 2017/

Training Course on HTGR/SMR Project Management, Russian Federation, 16 – 27 October, 2017

SV on SMR’s and floating 16 – 27 October, 2017 2017 2016 SV on floating NPP and fast reactor SMR technology. Training on floating NPP and fast reactor SMR technology 28.11- 16.12.2016 The First Crew of the Floating NPP Started Professional Training in St. Petersburg Branch of ROSATOM- CICE&T. 01.09.2015-15.03.2016 2015 Training Course “The Assessment of Advanced Pressurized Water Reactors Utilization in New-comer Countries” 09-13.11.2015 2013

The Training Seminar “Introduction to the Liquid Metal Fast SMR 2011 Technology” 29.09.-04.10.2013

The Technical Workshop on the topic “The Development of Curricula for Training of Foreign Specialists in Small-Power Nuclear Plants in Russia” 7.06.2011

Challenging Issue: Allocation of Budget for Training Language Barrier