SMR Technology Development in Russia and Capacity Building Supports for Embarking Countries
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“Rosatom Technical Academy” (Rosatom Tech) SMR Technology Development in Russia and Capacity Building Supports for Embarking Countries IAEA Technical Meeting on Technology Assessment of Small Modular Reactors for Near Term Deployment 2 – 5 October 2017 Tunis, Tunisia Vladimir Artisiuk © Rosatom Tech Contents 1. Nuclear technology in Russia in a nut-shell 2. New generation of Russian SMRs 3. HRD issues (NNP personnel) © Rosatom Tech 2 Nuclear Technology in Russia in a Nut-shell © Rosatom Tech 3 Russian Nuclear Power in a Nut Shell 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 © Rosatom Tech 8 2016: Main Achievements 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 © Rosatom Tech 9 New Generation of Russian SMRs © Rosatom Tech 10 SMRs in Russian Federation 1/2 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 © Rosatom Tech 11 SMRs in Russian Federation 2/2 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 © Rosatom Tech 13 SMR Fast Reactors with HLMC – SVBR-100 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 © Rosatom Tech 14 Fast Lead Cooled Reactor – BREST-OD-300 • 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 © Rosatom Tech 17 The First Crew of the Floating NPP Started Professional Training at St. Petersburg Branch of RosatomTech 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 © Rosatom Tech 18 In-Land NPP with RITM-200 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 © Rosatom Tech 19 2016 Achievements Nuclear Icebreakers Construction icebreaker “Arktika” is underway.