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LWR Spent Fuel Management for the Smooth Deployment of FBR

LWR Spent Fuel Management for the Smooth Deployment of FBR. T. Fukasawa 1 , J. Yamashita 1 , K. Hoshino 1 , A. Sasahira 2 , T. Inoue 3 , K. Minato 4 , and S. Sato 5. 1 Hitachi-GE Nuclear Energy, Ltd., 2 Hitachi, Ltd., 3 Central Research Institute of Electric Power Industry,

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LWR Spent Fuel Management for the Smooth Deployment of FBR

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  1. LWR Spent Fuel Management for the Smooth Deployment of FBR T. Fukasawa1, J. Yamashita1, K. Hoshino1, A. Sasahira2, T. Inoue3, K. Minato4, and S. Sato5 1 Hitachi-GE Nuclear Energy, Ltd., 2 Hitachi, Ltd., 3 Central Research Institute of Electric Power Industry, 4 Japan Atomic Energy Agency, 5 Hokkaido University ICSFM (IAEA-CN-178) Paper 11-02 (Vienna, 2010.5.31 - 6.4)

  2. Transition from LWR to FBR Reprocessing reduces LWR-SF and supplies Pu (MOX) for FBR deployment.

  3. Transition from LWR to FBR • According to the Japan’s Nuclear Energy Policy Framework published in 2005 by the Atomic Energy Commission, FBR will be deployed from around 2050 under its suitable conditions by the replacement of 60y old light water reactors (LWR). • The Framework mentioned that all spent fuels (SF) should be reprocessed (SF amounts reduction) and recovered Pu, U should be effectively utilized, while possessing no excess Pu. • Recovered Pu in Rokkasho Reprocessing Plant (RRP) will be utilized (consumed) in LWR-MOX. • Recovered Pu in the next reprocessing plant which will start operation around 2050 will be utilized for fast breeder reactors (FBR) deployment. • The next reprocessing plant(s) will treat SF from LWR-UO2, LWR- MOX and FBR. • Pu balance control by flexible fuel cycle system is quite important considering FBR deployment time and rate which are changeable.

  4. Typical FBR Deployment Pattern

  5. FBR FBR Transition Fuel Cycle Systems Two fuel cycle systems and several Pu balance control methods were investigated. If the FBR deployment rate decreases, Reference and Flexible Fuel Cycle Initiative (FFCI) systems will temporarily store LWR SF or FBR FF (Pu product) and recycle material (RM), respectively. Low proliferation resistance Temporary storage B FBR cycle B [2nd LWR reproc.] FBR reproc. A FBR fuel 100 % Reproc. Ref. system Fabrication FBR fuel LWR spent fuel Fabric. FP,(MA) FP,(MA) ~90% A: Rapid FBR deployment B: Slow FBR deployment Pu,(MA),U Recovered U Recycle material FBR cycle [2nd LWR reproc.] 100 % FBR reproc. A U recovery FBR fuel Pu,FP,MA,U Fabrication FFCI system ~90% LWR spent fuel B Recovered U FP,(MA) Extraction, Crystallization, Fluorination, etc. A: Rapid FBR deployment B: Slow FBR deployment Temporary storage

  6. Temporary Storage Materials Radiation dose from the storage material at 1m distance RM: Recycle material (Pu/FP/MA/~10%U), SF: Spent fuel, FF: Fresh fuel, MA: Minor actinides

  7. Mass Balance Analysis Variations Base case Factor No 58GWe 70GWe Nuclear capacity 1 2050 2040, 2060, 2090 FBR startup 2 FBR deployment rate Replace all LWR (60y) with FBR Replace ½ LWR, 1GWe/y constant, 3 2 step (1.5 - 0 - 1.5GWe/y) FBR core design (Breeding ratio) Oxide fuel compact core (1.10), Metal fuel (1.0) Oxide fuel high conversion core (1.13) 4 No limit / 30t Pu (20t Puf) 0t Pu Pu storage amount* 5 Excess Pu countermeasure FBR SF storage, FBR fresh fuel storage, Pu use in LWR Storage of FBR-FF (Pu product) / LWR-SF, RM 6 UO2 fuel (GWd/t): 33 (-2004), 45 (2005-2039), 60 (2040-) MOX fuel (GWd/t): 33 (-2024), 45 (2025-2039), 60 (2040-) 7 Burn up of LWR-SF 8 LWR capacity factor 80% (-2009), 85% (2010-2029), 90% (2030-) 9 LWR reprocessing RRP: 2008-, 2nd plant: 2048-, 3rd plant: 2088- ; or 2nd: 2048-2100 10 Reprocessing life 40y (LWR and FBR reprocessing plants) Reactor life 60y (LWR and FBR) 11 12 SF cooling time >3y (LWR-SF), >4y (FBR-SF) *30t Pu is same as RRP, Puf is fissile Pu (~2/3 Pu for LWR-SF)

  8. LWR-SF Amounts • Reprocessing is effective to reduce LWR-SF. • 2nd reprocessing plant is needed after RRP with higher capacity than that of RRP. • Much higher capacity or 3rd reprocessing plant is needed to treat all LWR-SF. • FBR deployment delay also necessitates the much higher capacity or 3rd reprocessing plant. • FFCI can reduce LWR-SF more effectively than reference system. 70000 70000 RRP (800t/y) only No reprocessing 60000 60000 50000 50000 U removal; 900t/y -> 1200t/y 40000 40000 Cumulative LWR spent fuel amounts (t) Cumulative LWR spent fuel amounts (t) 30000 30000 RM 20000 20000 2nd RRP (1200t/y) from 2050 to 2110 10000 10000 FFCI 0 0 2000 2000 2050 2100 2050 2100 Year Year Reference system FFCI system

  9. LWR reprocessing Amounts • LWR-MOX-SF with high Pu content is reprocessed at high FBR deployment rates. • Reference system needs 2nd and 3rd reprocessing plants (full function) of 1650 t/y capacities. • FFCI system needs 1200 t/y and 650 t/y capacities for 2nd and 3rd reprocessing plants (only uranium removal functions), respectively. LWR reprocessing amount (t/y) Year Year Reference system FFCI system

  10. FBR reprocessing Amounts • FBR reprocessing capacity increase at around 2090 is reasonable for the transition period. • Reference system needs 250 t/y capacity at around 2055 and 255 t/y at around 2095. • FFCI system needs earlier construction of FBR reprocessing plants that must also supply initial Pu for FBR deployment, 250 t/y capacity at around 2047 and 300 t/y at around 2088. FBR Reprocessing amount (t/y) Year Year Reference system FFCI system

  11. Pu Storage Amounts • Excess amount of Puf storage as reprocessing product is controlled below 20 t concerning the proliferation resistance. • Reference system with 20 t Puf storage limit affects the LWR-SF reprocessing amount. • FFCI system stores 132 t Puf (max.) in recycle material with high proliferation resistance, which does not affect the LWR-SF reprocessing amount. Puf storage amount (t) Year Year Reference system FFCI system

  12. LWR-SF Storage Amounts • 2nd reprocessing plant with high capacity is needed after RRP to reduce LWR-SF. • Reference system shows the second storage amount peak at around 2090 and needs AFR (away from reactor) storage facility even after 2080. • FFCI system can reduce LWR-SF more effectively than reference system. LWR-SF storage amounts (ktHM) Year Year Reference system FFCI system

  13. Cost Estimation Results

  14. Conclusions • The transition scenarios from LWR to FBR and the correspond fuel cycle (reference and FFCI) systems are investigated. As a result, the FFCI system can reduce the LWR-SF reprocessing capacity, LWR-SF reprocessing function, low proliferation resistant Pu storage amount, LWR-SF interim storage amount, and the total fuel cycle cost. • The most unique and important issue to be solved for the FFCI system is safety of the RM storage. Heat transfer property and hypothetical criticality accident are analyzed by using the data obtained from the simulated RM oxides, which clarifies the enough safety for heat removal and criticality. • These investigations show the effectiveness of the FFCI system for the transition period fuel cycle from LWR to FBR. This study includes the results of “Research and Development of Flexible Fuel Cycle for the Smooth Introduction of FBR” entrusted to Hitachi-GE Nuclear Energy, Ltd. by the Ministry of Education, Culture, Sports, Science and Technology of Japan (MEXT).

  15. U Recovery Technology Solvent extraction Crystallization UO2(NO3)2 crystal Spent fuel Spent fuel U solution Recovered U Dissolved solution Recovered U Dissolved solution Crystallization (Cooler) Extraction (Pulsed column) (Centrifugal contactor) Residue (Pu/FP/MA/U) Micro wave Residue (U, Pu, MA&FP) Denitration Recycle material Recycle material Denitration Fluoride volatility • U recovery residues are nitrate solutions • for solvent extraction and crystallization, • and fluoride powder for fluoride volatility. • Recycle material (RM) would be nitrate • solution, nitrate powder, fluoride powder • or oxide powder. • Oxide powder is most stable and aqueous • process is applied to reprocessing, thus • simulated oxide RM was prepared from • nitrate solution in this work.

  16. Preparation of Recycle Material Example of RM preparation method U recovery residue [Ref.: AVM process] Dust removal Calcinater (Rotary kiln) Liquid→Powder Heater Diameter control Recycle material (RM) Canister for RM storage To storage Filling Capping Decontamination RM preparation method must consider easy treatment, safe storage, and compatibility with FBR reprocessing.

  17. Storage of Recycle Material Recycle M. (estimated) Vitrified HLW Mater. • Specification Item FP,MA, Pu,U FP,MA, B-Si glass - Air cool, natural convection - Similar design to vitrified HLW storage facility - Criticality safety by the Pu amount limitation, etc. 1. Component 2. Form Granule Lump 1-3 2.7 3. Density (g/cc) 0.01-0.04 ~0.01 4. Heat (W/cc) ~15 0 5. Pu conc. (wt%) 6. After-treatment Reprocessing Disposal Recycle material storage facility (ex.) Ceiling slab Containment lid Recycle material Vitrified HLW Containment pipe Cooling air Air Air pipe 30C Support Floor crane Canister Canister Canister Cooling air Bottom support Storage area Cooling air >150D ~450D

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