Research Activities of JAEA Considering the Future Needs of Japan - PowerPoint PPT Presentation

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