1 Research Activities of JAEA Considering the Future Needs of Japan in Burnup Credit Implementation H. Okuno, K. Tonoike, K. Suyama* K. Okubo, G. Uchiyama October 27 th , 2009 * Present Affiliation: Ministry of Education, Culture, Sports, Science & Technology (MEXT)
2 Criticality Safety with BUC Nuclear Facility / Cask Handbook Power Plant Design & Operation Spent Fuel Burnup Nuclear Criticality Analysis Calculation Code Data Code SWAT JENDL MVP Spent Fuel Post Irradiation Critical Experiment / STACY Experiment (PIE) Benchmark Data October 27 th , 2009
3 Fuel Cycle Flow and BUC Status in Japan Off-site Storage No BUC No BUC Nuclear Fuel Power Cask with Fabrication Plant Spent Fuel Facility Fresh Fuel BUC Spent Fuel Pool & Dissolver Reprocessing Considering Actinides Only Plant Control Parameters: Burnup & Residual U-235 Enrichment Confirmed by Burnup Monitor Powder October 27 th , 2009
4 STACY Experiment with FP (Condition)* Uranium Solution with FP 6%EU, Sm, Cs, Rh, Eu Uranium Dioxide Fuel Rods 5%EU, PWR-type Heterogeneous System Simulating Dissolver * Study performed under the contract with Ministry of Education, Culture, Science and Technology of Japan October 27 th , 2009
5 STACY Experiment with FP (Critical Volume)* 600 Rh conc. ~1.3 g/L Cs conc. Critical Solution Level (mm) Eu sol. ~3.4 g/L Add Rh sol. Eu conc. Sm conc. Add ~0.02 g/L ~0.14 g/L Cs sol. 500 Add Final U sol. composition (Experiment No. 14) U : 323 g/L Sm sol. Sm : 0.12 g/L Cs : 2.8 g/L Add Rh : 1.2 g/L Eu : 0.02 g/L Free Acidity : 2.0N No FP (only U sol. fuel) U conc. ~330 g/L 400 1 2 3 4 5 6 7 8 9 10 11 12 13 14 Expriment No. October 27 th , 2009
6 STACY Experiment with FP (Concentration Worth)* 0 -100 Cs : -26.5 ± 1.4 Reactivity (cent) ¢/(g/L) -200 Rh : -131.4 ± 4.1 ¢/(g/L) -300 -400 Sm : -3293 ± 40 ¢/(g/L) -500 0 1 2 3 4 Sm, Cs and Rh concentrations (g/L) October 27 th , 2009
7 STACY Experiment with FP (Concentration Worth)* 0 -10 Reactivity (cent) -20 -30 Eu : -1348 ± 259 ¢/(g/L) -40 0 0.005 0.010 0.015 0.020 0.025 Eu concentration (g/L) October 27 th , 2009
8 STACY Experiment with Gd (Critical Volume) 900 Water Reflected Core Critical Solution Level (mm) Unreflected Core 800 700 600 500 U ~ 330 (gU/L) 400 0.00 0.02 0.04 0.06 0.08 0.10 Gd Conc. (g/L) October 27 th , 2009
9 Expected Trend of Japan in Future Longer LWR Era Improvement of LWR Economy e.g. Longer Fuel Reload Interval Higher Initial U-235 Enrichment Wider Application of BUC to SF Transportation (including Off-site Storage), etc. October 27 th , 2009
10 Discussion Point NPP Operator's Capability of BU Calculation for Criticality Safety Sophisticated BU Monitor Incentive of Electric Company Utilization of Experiment Facility PIE Facility, Critical Assembly, etc. October 27 th , 2009
11 Conclusions Only One Facility with BUC in JAPAN Possible Next Target : Transportation (including Off-site Storage) JAEA will promote R&D programs and develop technical capabilities. October 27 th , 2009
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