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Russian Approach to High Level Waste and Spent Fuel Management

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Russian Approach to High Level Waste and Spent Fuel Management WORKSHOP ON APPROACHES TO FINANCING A MULTINATIONAL REPOSITORY – CHALLENGES AND ALTERNATE APPROACHES State atomic energy corporation “Rosatom” Russian approach to high level waste and spent fuel management Khaperskaya Anzhelika State Corporation “Rosatom” December 11, 2018 OECD Headquarters The current situation in SNF & RW management Volumes of solid radioactive waste, both in storage and in final disposal SNF accumulation worldwide Is the spent nuclear fuel a resource or a waste? Strategic options 250 000 t of SNF 370 000 t SF in storage discharg 120 000 t ed from of NPPs worldwid e reprocesse d spent fuel STATUS AND TRENDS IN SPENT FUEL AND RADIOACTIVE WASTE MANAGEMENT IAEA NUCLEAR ENERGY SERIES No. NW-T-1.14, 2018 2 SNF Direct disposal SNF is stored for several decades and disposed in a geologic repository Finland, Sweden, USA, Canada, Germany 3 Reprocessing& Recycling today Reprocessing/Recycling – SNF is reprocessed, U and Pu reused as fuel in light water reactors or fast reactors – high level waste disposed in a geologic repository France, Russia, Japan, India and China ( countries with large and ambitions nuclear power programmes) Monorecycling today - MOX and repU fuel (up to 25% saving of nat U) World Map of MOX Fuel users 40 LWRs 14 AGRs 11 LWGRs 9 PHWRs World Map of repU Fuel users 4 Advanced Fuel Cycles LWR Open Fuel Cycle URANIUM DEMAND Without recycling 100% Recycling in light water 75% reactors BN-800 Recycling in fast reactors 5% Advanced nuclear system with LWR and FR , recycling U and Pu can provide long term (thousand of years) supply of low carbon electricity 5 5 Russian Nuclear Power Plants: 37 nuclear power units, 30 GW They produce 18,9% of the electricity generated in the country. • VVER-1000/1200: 15 units (13 units VVER-1000 + 2 units VVER-1200) in operation • 6 units under construction (Baltic NPP -2 units, Kursk NPP -2 units, Novovoronezh NPP-1, Leningrad NPP-1 unit ) •RBMK-1000: 11 units in operation •VVER-440: 5 units in operation till 2030, 3 units are in the course of decommissioning •EGP-6: 4 units in operation, decommissioning is scheduled for 2019-2021 •BN-600 (FR) 1 units in operation •BN-800(FR) 1 unit in operation •FTNPP 1 unit - "Academician Lomonosov" will replace Bilibino NPP (shout down in 2019-2021 years) •Research reactors, Ice-breakers •Submarines 6 Key Enterprises in RW and SNF Management and Nuclear Decommissioning Affiliates Atomic energy and nuclear industry enterprises - RW processing and storage - NPP - RW disposal - NFC facilities - SNF management - Science and technology - decommissioning Bilibino NPP Andreev Bay Sayda Bay Murmansk Kola NPP Gremikha Leningrad NPP Radium Institute Leningradsk Vilyuchinsk Kalinin NPP Smolensk NPP MSZ RADON Nizhegorodsk Kirovo- VNIIKhT Chepetsk Kursk NPP NIITFA Novovoronezh NPP Kazansk CMP UECC NO RW Dalur Saratovsk RIAR Sverdlovsk IRM Blaogveshchensk Beloyarsk NPP Rostov NPP Samarskoyeoye PA Mayak Balakovo NPP Khiagda Chelyabinsk PDC UGR SCC Khabarovsk Volgogradsk MCC NCCP NO RW NO RW ECP PIMCU Irkutsk Groznensk Novosibirsk Fokino AECC 7 SNFM infrastructure in Russia for closed NFC Reprocessing any type of SNF SNF Centralized wet and dry storage facilities Test Demonstration Centre for SNF reprocessing (commissioning in 2021) Underground research Partitioning and laboratory isotopes (commissioning in production 2024 ) Modernization of the HLW management infrastructure MOX-fuel for BN-800 fabrication 8 SNF Reprocessing at PA Mayak Routine reprocessing of WWER-440, BN-600, nuclear submarine, research and production reactor SNF. 2016 – starting the industrial reprocessing of RBMK-1000 SNF unsuitable for storage. Starting the industrial reprocessing of WWER-1000 SNF. AMB SNF: pilot shipment from Beloyarsk NPP in 2016, regular shipment – since 2017. Kola NPP Novovoronezh NPP Beloyarsk NPP PA Mayak NITI Research reactor SNF shipment activities Kurchatov Institute, MEPhI NIIP RIAR - Dimitrovgrad Moscow IPPE IRM IPPE, NIFHI - Obninsk NIIP - Moscow Region RIAR NITI, PNPI - Leningrad IRM - Ekaterinburg PA Mayak MEPhI, NRC and other Kurchatov Institute - 9 SNFM infrastructure in Mining &Chemical Combine Centralized wet and dry RBMK &VVER-1000 SNF MOX-fuel for BN-800 fabrication storage facilities Centralized wet SNF Test Demonstration Centre for SNF reprocessing storage facilities 10 Test Demonstration Centre for SNF reprocessing within SNF management complex in MCC «Dry» storage «Wet» storage for for VVER- VVER-1000 SNF 1000 SNF «Dry» storage for RBMK- 1000 SNF PDC 2015 – Construction of PDC’s first start-up complex is finished. 2021 – Full-scale PDC commissioning with a design capacity of 250 tons of SNF 11 Test Demonstration Centre - the first unit (research hot cells) Pilot-Demonstration Center 1st unit with a capacity of up to 5 t/y was completed. In 2016, technology testing has started. “hot cell” equipment 12 REMIX fuel – U& Pu multi - recycling in LWR reactors REMIX fuel is the mixture of U and Pu from LWR SNF reprocessing, with the addition of enriched uranium (natural or rep. U) . REMIX fuel enables multiple recycling of the entire quantity of U and Pu from SNF, with the 100% core charge and 20%- saving of natural uranium in each cycle. NPP irradiation cooling SNF reprocessing HLLW partitioning 5 SN year HL F W U-Pu mixture Rep Enrichmen . NPP U. t MA burning VVER / PWR recyc FABRICATION le U&Pu Non-separated U-Pu U-Pu mixture Enriched rep. U (5,2%) Unat. REMIX Fas repU Enriched nat U Nat U (4,4%) 13 13 Different types of REMIX fuel The Pu content is equal to the initial content in SNF Non-separated U- U-Pu Pu mixture REMIX-A On each recycle, the fresh fuel is added nat uranium Enriched rep. U - 0% with enriched uranium repU (enrichment of 19.75%). After the SNF reprocessing part of the rep U is not in demand Enriched nat U Unat. (19,75%) Number of recycles - 7 • The Pu content is equal to the initial Non-separated U- U-Pu Pu mixture content in SNF REMIX AB • On each recycle, the fresh fuel is added Enriched rep. U (5,2%) with repU enrichment repU. the repU (enriched to 5,2 %) and nat U and nat U feeding (enriched to 4.4%) Enriched nat U (4,4%) natU • Number of recycles - 7 • The Pu content is 4% REMIX-B Non-separated • On each recycle, the fresh fuel is added the repU U-Pu U-Pu mixture with nuclear materials • There is no nat U feeding (nuclear materials volume volume reduction Enriched rep. U (up reduction ) Uрег. to 6,2%) (without uranium • Number of recycles – up to 4 nat U - 0 % feeding) Nat U 14 REMIX FUEL STRATEGY ROAD MAP 2014 2016 2017 2018 2020 2030 FAs fabrication for NPP and RR Pilot project for 3 experimental REMIX FAs fabrication and irradiation • REMIX fuel performance • Start of irradiation in MIR RR and Balakovo NPP • Post-irradiation examination • Fuel fabrication facility • REMIX Fuel fabrication facility • 6 FAs REMIX • License for REMIX fuel loading • Safety case development for VVER-1000/1200 with REMIX fuel 100% core charge REMIX-fuel 100% core charge REMIX-fuel VVER-1000/1200 Irradiation of experimental FAs with REMIX fuel loading for irradiation to Balakovo NPP REMIX FAs is carried out in the MIR RR at NIIAR, Dimitrovgrad 15 Principal Chart of Two Component Nuclear Power Generation (System of Fast Neutron & Thermal Neutron Reactors) Generation (thermal neutron reactor) Closed Fabrication of fuel for LWR Fuel Conversion & LWR SNF R NFC enrichment EUP SNF management Accumulated SNF Enriched Products of UNF reprocessing UF6 U-235+Pu, Pu, MA, U-238 Storage of enriched Products of UNF reprocessing UF6 U-238 U-235, U-235+Pu, Pu Fabrication of fuel for FR Generation (fast neutron reactor) Fuel Disposal assemblies FR SNF (U-Pu+МА) Closed NFC efficiency grows along with ousting U-235-based fuel by U-Pu fuel 16 The R & D program for CNFC advanced technologies with BN-800 - Development and scaling of BN-800 MOX SNF management technologies (transportation , storage and reprocessing) ( 2019-2024); - Development of technologies of partitioning HLW and transmutation of MA in FR ( 2019-2034); - Development of the technologies of all NFC stages with mixed nitride uranium-plutonium fuel (irradiation of nitride fuel in BN-800, reprocessing, demonstration of fuel recycling)(2019-2027). 17 Extraction Cascade of the EF-35 Extraction ( from 1996) More than 1200 m3 of HLW was processed with Cs-Sr recovering ChCoDiC Different types of HLW cobalt dicarbollyde Filtration Raffinate after Extraction of 90Sr and 137Cs recovery of Cs and Sr Extract washing Further reprocessing O 90 HO n H Stripping of 90Sr and 137Cs Strip solution of Sr PEG and 137Cs Regeneration of extractant To vitrification polyethylene glycol Recycle extractant 18 TODGA-Based Technology for Extracting Trans Plutonium and Rare-Earth Elements. Extraction of Rare- Earth Elements, Am-241 and Сm-244 Using Elution - Displacement Chromatography O O CF3 C8H17 O C8H17 N N C8H17 C8H17 NO3 TODGA Fractions: TODGA meta- nitrobenzotrifluoride • Am 65 g, N, N, N ', N'-dioctyl diamide diglycolic acid Cm less than 0.8 %, Eu less than 0.1 %. • Cm 9 g, Am less than 6 % 19 Development of advanced technologies for HLW partitioning Maturing of HLW partitioning technology (with Am, Cm, RE, Cs-Sr recovering from HLLW and its separation) including modernization partitioning facility at Mayak plant – ( up to 2022) Developing and deployment facility of HLW partitioning facility at the MCC (up to 2025) Developing and maturing the technologies of Am, Cm oxides and mixed U-TPE oxides precipitation and production, the facility deployment (up to 2025) Developing and maturing the technologies for MA-bearing
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