for FR Cycle in Japan June 7, 2010 Hideyuki FUNASAKA JAEA - PowerPoint PPT Presentation

INTERNATIONAL FORUM «ATOMEXPO 2010» Current Status and Future Prospects for FR Cycle in Japan June 7, 2010 Hideyuki FUNASAKA JAEA

Contents  Introduction  Medium- to Long-term plan around 2050 and beyond -Transition from LWR cycle to FR cycle -  Near-term plan around 2015 -FaCT Project -  International collaboration  Summary * Fast Reactor Cycle Technology Development 2

Development Chronology in Reactor & Reprocessing 1970 2000 2030 2060 2090 年 Reactor GEN-I LWR GEN-II, III ALWR GEN-IV FR R&D 、 Demo.FR Reprocessing RT-3 3rd GEN. 2nd １ｓｔ Post-RRP GEN. GEN. AFCF 世界の潮流（ Global Global Trend of US West Valley FR UP2-400 FR UP3,2-800 Reactor & Reprocess 880t/y Plant FR UP2 RU RT-1 UK THORP Trend ）は次世代炉 -ing to Next Genera-- UK B205 etc JP JAEA TRP RU RT-2 La Hague Mod. 燃料サイクル tion JP JNFL RRP IN Kalpakkam PFRP CN Lanzhou-PP R&D Next GEN. 3

Japan’s Fundamental Strategy for Nuclear Fuel Cycle LEUO 2 Interim Storage fuel Facility R&D FR Spent fuel U/Pu/MA Spent fuel fuel LWR MOX fuel Fuel cycle U, Pu plant Reprocessing Industrial plant and social MA-free infra HLW HLW -structure MOX fuel plant Technical expertise HLW repository HLW repository Future FR fuel cycle Current LWR fuel cycle 4

Investigation on Transition from LWR cycle to FR cycle Example of preconditions for transition from LWR cycle to FR cycle  In order to replace all LWRs with FRs, it Installed Installed LWR LWR will take about 60 years as transition capacity capacity FBR FBR period from around 2050.  Next reprocessing plant (post-RRP Pu utilization in LWR Pu utilization in LWR plant) is envisioned around 2050. 2000 2000 2100 2100  Spent LWR UO2 fuels have to be reprocessed to introduce FRs in next Spent Spent Spent Spent Fuel Spent Fuel Spent Fuel Spent Fuel Spent Fuel Spent Fuel Fuel of Fuel of Fuel of of LWR- of LWR- of of of FBR of FBR reprocessing. LWR-UO 2 LWR-UO 2 LWR-UO 2 LWR-UO 2 LWR-UO 2 MOX MOX  Also reprocessing of spent FR fuels Pu Pu Pu Pu TRU TRU and LWR MOX fuels have to start Interim Interim around 2055-2060. storage storage  We need to figure out effective and Next Next rational image of next reprocessing Rokkasyo Rokkasyo Reprocessing Plant Reprocessing Plant Reprocessing Plant Reprocessing Plant plant. 5

FR Cycle Development Program in Japan 2050 (JFY) 2005 2010 201 5 Commercializatio 2015 Review & Basic Policy by MEXT Fast Reactor Cycle Technology Feasibility Study (1999-2005) n of FR Cycle Development Project (FaCT ） Facilities Most Promising Concept Fuel Cycle System FB FR System Validation of Economy & Decision of Innovative Tech. (2010) Approved Confirmation (2015) R Reliability &AEC R&D of Innovative Technologies 2025 Start of Demonstration FR Cycle Facilities HLW HLW Conceptual Design of Commercial & Advanced Aqueous Demonstration FR Cycle Facilities Reprocessing and Sodium-cooled Simplified Pelletizing Basic Design & Fast Reactor Fuel Fabrication Construction Commercialize 2015 d FR Cycle Experimental FR “Joyo” Conceptual Designs of Commercial Facilities and Demonstration Facilities with R&D Programs R&D at Prototype “Monju “  Demonstrating its Reliability as a R&D at Operation Power Plant “Monju “  Establish Sodium Handling Tech. 6 ◆ Cooperation with related Organization ◆ International Cooperation （ GNEP, GEN-IV, INPRO etc. ）

Development Targets and Design Requirements of Fuel Cycle Commercial Facility Safety and Reliability ○ Not influence on the significant radiation risk to public ○ Prevent the occurrence of off-site emergency ○ Establish the design concept possible to achieve the maintainability and repairability Sustainability Environment Protection ○ Keep the influence of the radioactive release on the environment through normal operation below the current fuel cycle Waste Management ○ Reduce the amount of radioactive waste to 1/2 - 1/5 of the current fuel cycle facilities ○ Recover more than 99.9% of U and TRU Efficient Utilization of Nuclear Fuel Resources ○ Possible to treat the SF with the heat power of 3kW/Assy (inn the case that the out-of core time is around 5 years) Economic Competitiveness ○ Fuel cycle cost should be < 340,000 JPY/kgHM (reprocessing ： < 180,000 JPY/kgHM, fuel fabrication ： < 160,000 JPY/kgHM Nuclear Non-Proliferation ○ Pure Pu should appear in any process 7 ○ It should be difficult to access the nuclear materials by handling low-decontamination TRU fuel

Improvement of Economics for JSFR MONJU :280MWe Breakdown list* Unit Construction Cost (JP Yen / kWe) 2.0M 2.0 Innovative Technologies *Example of first evaluation High Cr Steel, Others, 16% 16% 0.6M Large SG, Integrated IHX with 10% Pump, 10% 0.5M 0.48 2 loop heat DFBR Scale Merit Transport system, 26% Compacted R/V, :670MWe (to 1500MWe) 23% 0.4M Twin Effect 0.3M 0.2M ~0.18 1000$ line 0.1M JSFR :1500MWe × 2 Cost Estimation by NOAK and (FOAK) Overnight Cost, taking into account Learning Effect The unit construction cost of Monju is expressed as the construction cost divided by electric power. The unit construction cost of DFBR and JSFR are evaluated value 8

Typical Advanced Reprocessing Test in CPF Experimental Results 1 TOPO 0.9 Spent fuel 10 0.8 E DMDBTDMA 0.7 Distribution Ratio D dissolution fraction (-) 0.6 Disassembling/ CMPO 0.5 Shearing 0.4 TBP 1 0.3 Dissolution 0.2 0.1 0 0 60 120 180 240 300 360 420 480 540 600 Clarification dissolution time （ min. ） 0.1 Y La Ce Pr Nd PmSm Eu Gd Tb Dy Ho Er Tm Yb Lu Element U Crystallization Np valence adjustment Co-extraction MA recovery Co-stripping Extraction (U/Pu/Np recovery) chromatography Solvent regeneration Am, Cm U/Pu/Np High level U Concentration liquid waste Adjusting Pu content Revolutionary Type U U/TRU Evolutionary Type (product) 9 (product)

MOX Pellet Fabrication Tests by Simplified Pelletizing Method Pu-U Nitrate mixed Solution Adjusted Pu content Conversion by Binderless Microwave Heating granuation Granulation Flowable MOX Powder no additive Pressing Sintering Die lubrication (Grinding) Dissolving Inspectio n MOX Pellet Pellet Additional fabrication tests including Am-MOX fuel is going on. Fuel pin irradiation tests are planned, too. 10

International Cooperation of R&Ds on FR Cycle Kazakhstan Russia France U.S.A.  ODS cladding  Re-criticality elimination  CEA/JAEA Cooperation  U.S.-Japan Joint Nuclear irradiation, etc. mechanism (EAGLE on Nuclear R&D Energy action Plan project)  Reactor Research & (JNEAP) Advanced Nuclear Energy  Fast Reactor Technology System  Fuel Cycle Technology  Advanced Fuel Cycles, etc.  Simulation & Modeling  EDF/JAEA Cooperation  Safeguards & on Fast Reactor System Physical Protection  Design of Prototype/  Waste Management Demonstration Reactor  Operation/Maintenance, etc. Japan GIF Trilateral Collaboration  Sodium-Cooled FR  Sodium-cooled FR IAEA  design goals and high level requirements  Gas-cooled FR JAEA  INPRO for the prototypes  Very High Temperature Reactor  common safety principles  TWG-Fast Reactors  Super Critical Water Reactor  infrastructure needs, etc.  Irradiation test of MA bearing  Lead-cooled FR  TWG-Nuclear Fuel fuels (GACID project in GIF)  Molten Salt Reactor Cycle Options 11

Conclusions Japan is promoting the nuclear energy to supply stable energy and reduce CO 2 emission. • Medium to Long-term plan around 2050 and beyond Basic policy in Japan is closed fuel cycle. Therefore, in order to make the transition of LWR cycle to FR cycle around 2050 smoothly, intensive discussion in JAEC will be started in 2010. • Near-term plan around 2015 in FaCT Project Design study and R&D of innovative technologies are now in progress aiming at adopting of innovative technologies by judging of their applicability in JFY2010. Furthermore, study of future reprocessing technology would be discussed not only as FaCT project but also in the field of transition from LWR cycle to FR cycle. • International collaboration International collaboration is indispensable to efficient development of FR fuel cycle. JAEA expects further collaboration with concerned countries on FR fuel cycle by sharing the R&D items on the same target. 12