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Advanced Fuel cycle Activities in IAEA H.P. Nawada and C. Ganguly

Advanced Fuel cycle Activities in IAEA H.P. Nawada and C. Ganguly Nuclear Fuel Cycle and Materials Section, Division of Nuclear Fuel Cycle and Waste Technology, Department of Nuclear Energy, IAEA, Vienna. Director General. Department of Management. Department of Nuclear Safety.

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Advanced Fuel cycle Activities in IAEA H.P. Nawada and C. Ganguly

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  1. Advanced Fuel cycle Activities in IAEA H.P. Nawada and C. Ganguly Nuclear Fuel Cycle and Materials Section, Division of Nuclear Fuel Cycle and Waste Technology, Department of Nuclear Energy, IAEA, Vienna Nawada INPRO Oct 2007

  2. Director General Department of Management Department of Nuclear Safety Department of Technical Cooperation Department of Nuclear Sciences and Applications Department of Safeguards Department of Nuclear Energy INIS Section Planning and Economic Studies Section VIC Library Section Division of Nuclear Fuel Cycle and Waste Technology (NEFW) Division of Nuclear Power(NENP) Waste Technology Section (WTS) Nuclear Fuel Cycle & Materials Section (NFCMS) Nawada INPRO Oct 2007

  3. Major Programme 1 B of IAEA : Nuclear Fuel Cycle & Materials Technologies Mission Statement To promote development of nuclear fuel cycle options that are economically viable, safe, environment-friendly, proliferation-resistant and sustainable.To promotes information exchange on: • exploration, mining and processing of uranium and thorium • design, manufacturing , and performance of nuclear fuels • management of spent fuel, including storage & treatment of spent fuel & recycling of plutonium & uranium fuel, and • development of advanced and innovative nuclear fuels and fuel cycles. Nawada INPRO Oct 2007

  4. IAEA Programme - Nuclear Fuel Cycle & Materials Technologies Nawada INPRO Oct 2007

  5. Subprogramme B 4 : Topical Nuclear Fuel cycle Issues • Objectives: • Reducedecay heat, volume & radiotoxicityof high level waste by Partitioning & Transmutation to minimize space requirement in repository • Advanced fuels and advanced fuel cycles, utilizing Pu and Minor Actinide(MA: Np, Am & Cm) based fuels & fuel cycle options • Efficient utilization of natural resources (U &Th) by multiple recycling of fissile & fertile materials and Minor Actinides in “closed” nuclear fuel cycle • Ensuring “Safety &Security” and “proliferation – resistance” (intrinsic and extrinsic) in nuclear fuel cycle activities • Multilateral/ Regional Fuel Cycle Facilities : working on the principle of “assurance of fuel supply” and “assurance of proliferation – resistance” Nawada INPRO Oct 2007

  6. Developments in Innovative Nuclear Energy Systems  Thorium fuel cycles Nawada INPRO Oct 2007  Disposition of weapon materials

  7. Once-through “open” cycle – long term storage of spent fuel followed by disposal; • Deferring a decision ( wait & see ): interim storage; • Classical “closed” cycle – spent fuel reprocessed, Pu + U recycled and waste [ fission products & Minor Actinides(MA)] disposed; • Advanced “closed” cycle – spent fuel reprocessed, Pu+U+ MA recycled & fission products disposed Nawada INPRO Oct 2007

  8. Coordinated Research Project (CRP) on Study of process-losses in separation processes in partitioning and transmutation systems in view of minimizing long term environmental impacts Fuel cycle Nuclear fuel material Solidification Matrix Reactor M Spent fuel storage Process Losses Repository waste IMPACT Fuel Fabrication Separation Process Environment Nawada INPRO Oct 2007

  9. Nawada INPRO Oct 2007

  10. CRP Objectives • Minimization of losses • Advanced characterization methods for actinides • Separation criteria to minimize environmental impact • List of critical radio-nuclides • Defining environmental impact associated with partitioning processes • Basic studies to compare dry partitioning process with aqueous partitioning processes • Defining proliferation resistance attributes Nawada INPRO Oct 2007

  11. Minor actinide fuel / target will be the critical link between partitioning and transmutation Working Group on Process and property of minor actinide compounds and alloys for nuclear fuel and target for incineration in thermal and fast neutron spectra Issues in MA-based fuel development • MA-based fuel must be fabricable using remote processes • The fuel must be compatible with the fuel recycle process • The fuel form must provide robust containment for fission products • The technologies of minor actinide-bearing-fuel materials are not well established (although, for dilute minor actinide contents, the properties should not differ substantially from the base U-Pu-bearing materials) Nawada INPRO Oct 2007

  12. Nawada INPRO Oct 2007

  13. Joint effort from NEFW and INPRO Nawada INPRO Oct 2007

  14. TM findings: TM-LMFR provided opportunity fostering information exchange among interested IAEA Member States in innovative nuclear fuel cycle technologies It was recognized that nuclear fuel development for LMFR, like MOX fuel, U-metal and nitride as well inert matrix fuel will provide a major basic types of fuels With regards to the fabrication and reprocessing/recycling technologies the main focus will be done to the wet and dry processes As regards to the fabrication and reprocessing technologies, the participants have recognized that in the short term prospects, advanced aqueous methods are considered as the major methods for MOX fuel It was noted that for the long term prospects (after 2030) dry reprocessing technology may prove their attractiveness for vibro-packed MOX, metal U-Pu and UPu-N fuel. Wet technology may apply for nitrides fuel as well Future plans: 1.) Technical meeting on ‘Developmental needs for deployment of advanced fuel cycles’, Dec 10-12 2007, Vienna 2.) Technical meeting on “Conventional and innovative fuels for fast reactors”, Dec 17-19 2007, Vienna 2.) Agency has plans to conduct an International Conference on Fast Reactors and its Fuel Cycle in 2009 Nawada INPRO Oct 2007

  15. IAEA Minor Actinide Property Database (MADB) • Bibliographic database on thermodynamic and thermophysical properties of minor actinide (Np, Am, Cm) metals, alloys and compounds • Access on the internet with some search and filter capabilities (www-nfcis.iaea.org) Plan for initiation of Coordinated Research Project (CRP) for the assessment mixed oxide systems such as urania-plutonia, urania-thoria and thoria-plutonia (2008-2010) Nawada INPRO Oct 2007

  16. Management of Reprocessed uranium • Benefits of Recycle of Reprocessed U (RepU) and Pu: • Reduces the radiotoxicity and volumes of waste • Effective utilization of raw resources for energy generation, SWUs & repository space • Reduces also fresh milling and mill tailings and associated radiotoxicity • For some Member States –resources are very critical • Similar in-reactor performance as standard fuel Challenges in Recycle of RepU: - Economics - Proliferation – concern - Technical viability • Fuel Design • Higher neutron absorption/poison effect in thermal reactor spectrum due to presence of U236 • Fuel Manufacture • Higher radiological effects • - Internal dose implications due to higher U234 concentration • - External dose implications due to presence of U232 Nawada INPRO Oct 2007

  17. Technical meeting on “Reuse options for Reprocessed uranium” 29-31 Aug 2007 at Vienna • There were 24 technical presentations from 55 Experts from 14 Member States, and OECD /NEA • Technical programme: • 1.) Management of RepU: recent analyses of IAEA and OECD; • 2.) Storage, packaging, and transport of RepU; • 3.) RepU fuel assembly manufacturing; • 4.) Processing of RepU; • 5.) Utility experience and potential use; and • 6.) Economics, market aspects, and Long-term perspectives of RepU utilization • Floor Discussion: • 1.) RepU: too hot to handle? • 2.) Can suppliers meet utilities’ current and future needs? and • 3.) Management of RepU: what do we have? What do we need? What is missing?” Nawada INPRO Oct 2007

  18. Recycle of RepU • Direct Recycle • Flux flattening in Heavy Water Reactors (HWR) • Use of RepU to Increase Fuel Burn-ups in HWR (SEU category) • Use of RepU in Fast Reactors • Physical re-enrichment (LWR, RBMK, AGR) • As Matrix for MOX fuel for LWR, PHWRS, FBRs • Blending with • HEU • LEU • NatU Nawada INPRO Oct 2007

  19. Inert Matrix Fuel (IMF) . • Minimizing “proliferation risk” of plutonium by the use of fertile-free fuel • Minimizing “Minor Actinides” and in turn radiotoxicity in waste • IMF in existing Nuclear Power Plants Nuclear fuel cycle extensions showing both IMF multi-recycling or “once through then out” (OTTO) options: The arrows (1,2,3) denote the conventional UOX once-through fuel cycle; the arrows (4,5) introduce the reprocessing step where Pu is produced and stocked; arrows (5,7,3) or (6,7,3) represents IMF in OTTO mode and arrows (5,7,4,8) indicates IMF multi-recycling Nawada INPRO Oct 2007

  20. IAEA-TECDOC-1516 on ‘Viability of Inert Matrix Fuel in Reducing Plutonium in Reactors’ 1. Overview 2. Potential IMF application; environmental, fuel cycle aspects, economic, non-proliferation aspects, historical before 80’s, current programs 3. R&D activities for IMF qualification 4. Country Specific programs 5. International programs: Irradiations 6. Outlook and Results Nawada INPRO Oct 2007

  21. 1.8% SEU (Th + Pu)O2 24 pins Water Tube ThO2 (Th + U233)O2 30 pins Displacer Rod Technical document (IAEA-TECDOC-1450) on Thorium fuel cycle options: Potential benefits and challenges • RATIONALE FOR THORIUM-BASED FUEL CYCLES • IMPLEMENTATION SCENARIOS AND OPTIONS • CURRENT INFORMATION BASE • FRONT-END ISSUES AND CHALLENGES • BACK-END ISSUES AND CHALLENGES • PROLIFERATION RESISTANCE • ECONOMIC ISSUES • Fuel cycle studies • once-through thorium • “direct-self-recycle” AHWR Fuel cluster Nawada INPRO Oct 2007

  22. Thorium fuel cycle • Very large thorium resources could be utilized for nuclear energy generation apart from increasing efficiency of U-resource utilization • Neutron yields of 233U in the thermal and epithermal regions are higher than those of 239Pu and also , 232Th is a better ‘fertile’ material than 238U in thermal reactors • Improved operating margins due to better thermo-physical properties of ThO2 fuel even at high burnup, compared to those of UO2 fuel • Potential for fuel cycle cost reduction, the reduction in 235U enrichment requirements • Reducing long-lived radioactive waste inventories by diminishing the production of plutonium and minor actinides • Th-based fuels and fuel cycles have intrinsic proliferation-resistance due to the formation of 232U via (n,2n) reactions with 232Th, 233Pa and 233U. The half-life of 232U is only 73.6 years and the daughter products have very short half-life and some like 212Bi and 208Tlemit strong gamma radiations Technical Meeting on Thorium-based Fuels and Fuel Cycle Options for Pressurized Heavy Water-cooled Reactors (PHWR), Light Water Reactors (LWR) and High Temperature Gas-cooled Reactors (HTGR), 22 to 25 October 2007, Istanbul, Turkey in cooperation with Turkish Atomic Energy Authority, Scientific Secretary: Mr. C Ganguly Nawada INPRO Oct 2007

  23. Status and Trends in Gas-Cooled Reactor fuels • The recent increased interest in Gas-cooled reactor fuels (viz., coated particle fuel) • Generation-IV Reactors • Deep-burn concept to destroy trans-uranic elements • Inert Matrix fuel approach to burn weapon-grade Pu • Generation of Nuclear Hydrogen Prismatic block US, Japan, Russia and France Pebble Bedcoated particle fuels embedded in spherical shapeGermany, South Africa, China 1. Coated fuel particles for HTGR Pyrolytic Carbon Silicon Carbide PorousCarbon Buffer UCO Kernel TRISO Coated fuel particles (left) are formed into fuel rods (center) and inserted into graphite fuel elements (right) Pebble fuel elementPebble has diameter of 60 mm COATED RTICLES COMPACTS Nawada INPRO Oct 2007 Triso coated particle

  24. Technical meeting on current status and future prospects of gas-cooled reactor fuels • Develop manuals/handbooks and best practice documents for use in training and education in coated particle fuel technology • Cooperating EC-RAPHAEL EURO-COURSE on ‘Coated particle fuel’ Dec 4-7, 2007, NRG, Patten, The Netherlands, Nawada INPRO Oct 2007

  25. The HTR Fuel and Materials Factbook Develop manuals/handbooks and best practice documents for use in training and education in coated particle fuel technology Outline of the document as following: 1. Introduction; 2. Energy and Electricity; 3. Nuclear Hydrogen Generation; 4. Nuclear Fuel; 5. Structural Materials; 6. Fuel Structural Materials; 7. Particle Fuel Manufacturing and QA/QC Activities; 8. Sphere Making; 9. Fabrication of Fuel Compacts; 10. Block Making; 11. Fuel Chemistry; 12. Fuel Failure Mechanisms; 13. Fission Product Retention; 14. Accident Testing; 15. Particle Modeling; 16. Quality Control and Quality Assurance; 17. Spent Fuel Management; and 18. The Way Forward. Nawada INPRO Oct 2007

  26. EUROCOURSE EUROCOURSE on coated particle fuel on coated particle fuel Seminar 2 / 3 Seminar 2 / 3 “ReActor for Process heat Hydrogen And ELectricity generation” “Plutonium & Minor Actinide Management in Thermal High Temperature Reactors” Projects of the EURATOM 6th Framework Programme “ReActor for Process heat Hydrogen And ELectricity generation” “Plutonium & Minor Actinide Management in Thermal High Temperature Reactors” Projects of the EURATOM 6th Framework Programme “ReActor for Process heat Hydrogen And ELectricity generation” “Plutonium & Minor Actinide Management in Thermal High Temperature Reactors” Projects of the EURATOM 6th Framework Programme Nawada INPRO Oct 2007

  27. The EUROCOURSE (Dec 4-7, 2007, NRG, Patten) on coated particle fuel will cover the following main topics: - General  Information on V/HTR - Coated  Particle Fuel Design - Fuel  Fabrication and Coating Technologies - Fuel  Irradiation and PIE - Fuel  Waste Processing and Storage Working language: English Nawada INPRO Oct 2007

  28. Technical Basis for Increasing the Proliferation Resistance of Nuclear Energy Systems and Fuel Cycles • Synergistic HWR/LWR Fuel Cycles • DUPIC • Fast Reactor and Pyrometallurgical Reprocessing • Thorium Nuclear Energy Systems and Fuel Cycles • Sodium-Cooled Fast Breeder Reactor System with Advanced Aqueous Reprocessing • Small Reactors with Extended Life Core • HTGR/PBMR Reactors • Molten-Salt Reactors • Accelerator Driven Systems • Nuclear Energy Systems and Fuel Cycles with Other Fuels Nawada INPRO Oct 2007

  29. Protected Plutonium Production (P3) Project • Protected Plutonium Production (PPP) and utilization is a collaboration between Tokyo Institute of Technology and IAEA • on “intrinsic proliferation resistance” of growing Plutonium inventories (~1900 tons) through utilisation of Minor Actinides (MA) inventories (~200tons)[MA: Np,Am & Cm]. • PPP addresses the challenges of introducing enriched uranium (<5%) oxide and MOX fuels containing < 1% MA in operating water –cooled power reactors and MA bearing fuel and blanket (U-238/Th-232) for LMFR , with respect to manufacturing, reprocessing, safety and economics Nawada INPRO Oct 2007

  30. Conclusions: Recent policy issues on fuel cycle choices considering recycling of fissile materials have generated large interest in the development of advanced fuel cycles The realization of advanced fuel cycle technologies calls for international collaborations to develop complex technologies Apart from solving the technological feasibilities, future R&D should also pay attention to economics as well as environment, and non-proliferation. Technical Meeting on “Development Needs for Deployment of Advanced Fuel Cycles” at IAEA Headquarters, VIC, Vienna 10-12 Dec 2007 Objectives of the meeting are: 1. Criteria for deploying advanced fuel cycles; 2. Simulation of a back-end in advanced fuel cycles; 3. Requirements for reprocessing and re-fabrication of advanced fuels in multiple forms Nawada INPRO Oct 2007

  31. Thank you for your kind attention h.nawada@iaea.org Nawada INPRO Oct 2007

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