INPRO Steering Committee VIC, July 02-04, 2007

1. CP RUS-2 (AINFC-CNFC) Joint Initiative on Assessment using INPRO Methodology on the basis of general characteristics and input/output parameters of Advanced and Innovative Nuclear Fuel Cycles within large scale INS based on Closed Nuclear Fuel Cycle concept to satisfy principles of sustainability in 21-st Century INPRO Steering Committee VIC, July 02-04, 2007

2. Background • Reference to latest international statements and declarations regarding CNFC • RF national strategy • US Nuclear Society • IAEA Scientific forum • RF-USA bilateral cooperation

3. Background • Currently INPRO Joint Study on Assessment of INS based on closed nuclear fuel cycle with fast reactors has initiated JI GAINS to make a new step to a more specific task of developing recommendations on arrangement of the global and national INS’s • The Proposed Project will provide link, input, data, support and inter-coordination and connection with INPRO GAINS Project

4. The overall objectives • Provide for the decision making: • Overview of feasible technical and economically sound alternatives of transitions to closure of INS nuclear fuel cycle (NFC), based on available and promising advanced and innovative nuclear fuels and fuel cycles (AINFFC) • Identification of different promising AINFC options applicable to the conditions of a participated Member States, • Assessment using INPRO Methodology of different AINFCFC options for each INSCFC based on jointly agreed input/output parameters, general characteristics of NFC with; • Provide a fissile and fertile nuclear material flow analysis for each reference alternative of INSCFC • Identify of level of uncertainties in the results of assessment • Identify near, medium and long-term institutional measures and technical solutions for each reference alternative of closure of INS nuclear fuel cycle, based on assessed options of INFCFC to meet sustainability objectives in 21-st Century, • Consider and make recommendations on AINFCFC options to be used for International and/or Regional Nuclear Fuel Cycle Centers • Determine specific issues in safety, waste management, proliferation resistance, economics for more detailed elaboration in the framework of INPRO Collaborative Projects or on multi- and bilateral basis.

5. The following tasks may also be solved during the Project implementation activity • Identification of experimental studies and tests for mastering FRs fuels, refinement reprocessing processes and waste disposal concepts jointly or/and nationally ; • Development of recommendation on vision, structure of a complete NFC/NFC’s and their facilities of commercial INS of the first generation based on CNFC-FR for further jointly and/or nationally • designing, • commissioning, • construction and operation • Identification of R&D on the advanced and innovative designs and processes of CNFC-FR providing break-through characteristics of sustainable energy supply • Development of recommendations on creation of national and international infrastructure for the development and deployment of the INS based on CNFC-FR including :

6. Method of Assessment • The Project is focused on assessment using INPRO Methodology of advanced and innovative nuclear fuel cycle technologies within large scale Innovative Nuclear Energy System based on Closed Nuclear Fuel cycle concept to satisfy INS CFC sustainability objectives in 21-st Century. • The INPRO methodology will provide to the Project guidance in assessing ability of large scale INSCNFCto assure • reduction of nuclear wastegeneration • stable and low prices of nuclear fuel and its availability, • enhancement of • nuclear fuel and fuel cycle technology economics, • safety, • performance,. • Joint Assessment of AINFCFC of INSCFC using INPRO methodology is going to be done on the basis of jointly selected and agreed input/output parameters, general characteristics of AINFFC to satisfy INSCNFC sustainability.

7. Method of Assessment • Jointly agreed models and computer codes are going to be used for NFC modeling • No commercial and confidential information is going to be handled within the scope of the Project activity.. • The various jointly selected and agreed nuclear fuel and AINFCFC options based on national preferences and long term strategy of INSCFC development and deployment may be considered as a references for the joint assessment studies • Decentralized on-site reprocessing concept and large reprocessing plant concept for NFC of INCCFC scenario may be considered as a subject of Joint Assessment.

8. Project Implementing arrangements • In order to implement the Project, the competent authorities in interested INPRO Members should conclude appropriate implementation agreements. • These agreements should include • financial arrangements, • membership eligibility • termination clauses, • provisions for effective protection and allocation of background proprietary information and generated intellectual property

9. Relationship with Nuclear Power development programs • Proposed Assessment Studies • are a very important for optimization possible scenarios of global and national large scale INS development and associated closed nuclear fuel cycle • may be considered as an international integrative project with GIF, GNEP, AFCI under IAEA aegis

10. Interactions with GAINS • GAINS provide input to the Project regarding • general scenarios, • data on structure and reactors composition of INSCFC on a global and national levels in a long term prospects based on energy demands projections, • scale of the national nuclear energy system development strategies. • The Project on the basis of these input will elaborate • prospective NFC alternatives of a different AINFCFC options for each INSCFC scenario with identification • of most promising options based on the jointly agreed criteria in order to reach maximum utilization of nuclear material potential, • its availability, competitiveness, minimize waste generation, excellent safety and optimal NFC structure. • The Project provides to GAINS • Assessment results of a different AINFCFC options for each INSCFC scenario with identification of most promising options • GAINS further considers and adjust • the structure of INSCFC to be consistent with a structure and capability of AINFCFC which are going to serve CNFC on a global and national levels and make appropriate recommendations

11. INPRO CP-JI in the area of INFC Global INS CP RUS-1-GAINS IAEA Multilateral Nuclear Approaches (MNA) CP RUS-2- AINFCT-CNFC Innovative NFCT Advanced NFCT Current NFCT

12. CPP RUS-2 Input: The various jointly selected and agreed nuclear fuel and AINFCFC options based on national preferences and long term strategy of INSCFC development and deployment, for example the following: • RIAR Dimitrovgrad Dry Process (DDP) for production and reprocessing of FBR MOX fuel • DOVITA fuel cycle: DDP for production and reprocessing MA bearing oxide fuel • Khlopin Institute Simplified Reprocessing Concept for LWR SNF reprocessing Simplified PUREX and Supercritical Fluid Extraction • Combination of Fluoride Volatility process and DDP for LWR SNF reprocessing • Thorium fuel pyrochemical reprocessing • Any other AINFCFC of INSCFC proposed and agreed by participating INPRO Member States • Decentralized on-site reprocessing concept vs. large reprocessing plant concept for NFC of INCCFC scenario.

13. General results • Project results will increase the capabilities of interested Member States for • policy making and strategic planning, • technology holders for • development and implementation of safe, reliable, economically efficient, proliferation resistant and environmentally sound innovative nuclear reactors and fuel cycle programs

14. Specific results • Overview of feasible technical and economically sound alternatives of closure of INS nuclear fuel cycle (NFC), • Assessments results of different AINFFC options for closure of INS nuclear fuel cycle, • Selection of promising AINFFC options applicable to the global or/and conditions of a participated Member States, • Recommendations on near, medium and long-term institutional measures and technical solutions for each reference scenario of closure of INS nuclear fuel cycle, based on assessed options of INFFC to meet INS sustainability objectives, • Recommendations on specific technical, economics and institutional issues that are important for the AINFFC of INSCFC introduction including International Nuclear Fuel Cycle Centers issues and proposals for Collaborative Projects in the framework of INPRO or on multi- and bilateral basis .

15. Potential COLLABORATOR • Canada, China, France, India, Republic of Korea, Russian Federation, Japan, Ukraine, USA and other interested MS’s

16. Current and developing reprocessing methods in Russia

17. Nationaltechnologies for INS CNFC-FR

18. Complementarity of national conditions that emphases the need for enhancing collaboration within INS based on CNFC-FR

19. Possible flows for BN type reactors and LWR SNF • Reprocessing of LWR SNF is possible for two tasks • recovery of slightly enriched uranium for re-enrichment (SNF with medium burn-up) • Recovery of Pu and MA for burning • Program for BN type reactors introduction (BN-800,BN-1600,BREST) demands Pu (+ MA) • One initial loading of BN-800 demands 160-220 tons of LWR SNF (+ annual additions) • Uranium after recovery of Pu(+MA) could store instead LWR SNF with 5-10 times volume reduction

20. National Complex “VVER type reactors + large Reprocessing plant “ U for enrichment or disposal VVER Local Complexes “Fast reactor + on-site reprocessing” Pu SFAs Reprocessing Plant SFAs storage Regional intermediate scale Reprocessing Plants MOX FR FR FR SFAs Triple-level Concept of future Russian NFC.RIAR view

21. Thank you for your attention

22. Additional materials Current world-wide context Status on middle of 2007

23. STRATEGY OF NUCLEAR POWER DEVELOPMENT IN RUSSIA • in the first half of the 21st century declares that “The successful operating record of the first civilian nuclear power facilities gave rise to the concept of nuclear power • – thermal reactors generate energy and accumulate plutonium for the startup and concurrent deployment of fast reactors; • – fast reactors step in to provide large-scale growth of nuclear power which will gradually replace traditional fossil energy sources. • The strategic objective was to obtain inexhaustible resources of cheap fuel – uranium and, possibly, thorium – through nuclear breeding.

24. Milestones of water reprocessing in Russia • Year 2006 – 600 mtHM/year (VVER-1000 + RBMK-1000) + imported fuel • Year 2020 – 1000 mtHM/year (mostly VVER-1000) • MCC Dry Store capacity might be exhausted around 2025 • MCC Wet AFR Facility in operation from 1985 with design life time 30 years • 2006 – 2008 – R&D for innovative technologies development • 2008 – 2010 – Initial Data for preliminary Design of the Experimental Demo Center (EDC) at MCC • 2007 ­– 2010 – EDC Design • 2010-2012 гг. – Construction of EDC • 2013-2015 гг. – Start of Testing and Operation, Initial Data for the Design of Industrial Scale Plant • After 2025 – operation of Industrial Scale Plant

25. R&D on SNF Pyrochemical Reprocessing in a World • Oxide SNF reprocessing into Oxidein molten chlorides – RIAR (Russia), JNC/JAEA (Japan) • Oxide SNF reprocessing into Metallicfuel in molten chlorides – CRIEPI (Japan), ITU (EU) • Nitride SNF reprocessingin molten chlorides – JAERI/JAEA (Japan), RIAR, Bochvar Institute (Russia) • Metallic SNF reprocessingin molten chlorides – ANL (US), CRIEPI (Japan) • LWR SNF metallization in molten chlorides – KAERI (Korea), RIAR (Russia) • HLW partitioning in molten salts – CRIEPI (Japan), RIAR (Russia), KAERI (Korea), CEA (France), ITU (EU) • Fluoride volatility processes – CRIEPI, Hitachi/TEPCO (Japan), Kurchatov Institute, RIAR (Russia), Rez (Cech Rep.) • Others applications(MSR fuel, RTILs, molten molybdates) RIAR, ANL, CRIEPI, JAEA, CEA

26. International cooperation in the field of advanced FC. RIAR research needs. Blue – current and past activities, red – planning, discussing and desired, black – without RIAR, but in any case – in all topics and cases RIAR is ready to participate

27. World-wide SNF reprocessing current situation Only one subject of SNF reprocessing world market - AREVA 2007 Plants • France – 1600 t/year – Gen-2 (AREVA) • Japan – 800 t/year –Gen-2(AREVA participation) • Russia – 100 t/year – Gen-1 • ……. New Plants before 2040 • 2025 – US – 3000 t/year – Gen-3, UREX+ (+AREVA?) • 2025 - Russia – 1500 t/year – Gen-3, PUREX? (+AREVA?) • Around 2025 –China– 1500 t/year – Gen-3, PUREX, PUREX (+AREVA?) After 2040 года • France – new plant – Gen-4 • Japan – new plant for reprocessing LWR and FR SNF, Gen-3+ • …………

28. CP RUS-2 Place, Role and Destination • Develop the Transition Scenarios from current NFCT to future GAINS • Compare the Transition Scenarios from point of view of economical, technical and temporal feasibility • Develop the recommendations for different Transition Scenarios

29. Examples of Transition Scenarios (1) Evolutionary Transition Scenario Long-term horizon (2050) • Existing Large Reprocessing Plant for LWR SNF based on water technology • Adaptation the water reprocessing technology to FR SNF • Large centralized Reprocessing Plant for FR SNF based on water technology • Long-term horizon (after 2040-2050) development of AINFCT (Pyro) for CNFC Countries – Japan (Russia? – we haven't yet final decision))

30. Examples of Transition Scenarios (2-1) Combined Transition Scenario -1 Middle-term horizon (2025) • New Large Reprocessing Plant for LWR SNF based on water technology (2020-2025) • Accelerated development the Pyro AINFCT for FR SNF reprocessing • Reprocessing Plant for FR SNF (2025) Countries – US, (Russia)

31. Examples of Transition Scenarios (2-2) Combined Transition Scenario - 2 Long-term horizon (2040) • Existing Large Reprocessing Plant for LWR SNF based on water technology - till 2040 • Development the AINFCT for FR SNF reprocessing • Large Reprocessing Plant for Gen-IV Reactors SNF - 2040-2050 Countries – France

32. Examples of Transition Scenarios (3) Accelerated Innovative Transition Scenario Middle-term horizon (2025) • New Large Reprocessing Plant for LWR SNF based AINFCT (Fluoride volatility + Pyro) – 2025 • Accelerated development the Pyro AINFCT for FR SNF reprocessing • On-Site Reprocessing Plants for FR SNF -2025 Countries – Russia?, India?