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 27th, 2009

* Present Affiliation: Ministry of Education, Culture, Sports, Science & Technology (MEXT)

October 27th, 2009

2

Criticality Safety with BUC

Critical Experiment / Benchmark Data Criticality Analysis Code Nuclear Data Facility / Cask Design & Operation Post Irradiation Experiment (PIE) Burnup Calculation Code Nuclear Power Plant Spent Fuel Spent Fuel MVP STACY JENDL SWAT Handbook

October 27th, 2009

3

Fuel Cycle Flow and BUC Status in Japan

Nuclear Power Plant Fuel Fabrication Facility Fresh Fuel Reprocessing Plant Off-site Storage Cask with Spent Fuel Powder No BUC No BUC BUC

Spent Fuel Pool & Dissolver Considering Actinides Only Control Parameters: Burnup & Residual U-235 Enrichment Confirmed by Burnup Monitor

October 27th, 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 27th, 2009

5

STACY Experiment with FP (Critical Volume)*

1 2 3 4 5 6 7 8 9 10 11 12 13 14 Expriment No. 400 500 600 Critical Solution Level (mm) No FP (only U sol. fuel) Sm sol. Add Cs sol. Add Rh sol. Add Eu sol. Add

U conc. ~330 g/L U : 323 g/L Sm : 0.12 g/L Cs : 2.8 g/L Rh : 1.2 g/L Eu : 0.02 g/L Free Acidity : 2.0N Final U sol. composition (Experiment No. 14) Sm conc. ~0.14 g/L Cs conc. ~3.4 g/L Rh conc. ~1.3 g/L Eu conc. ~0.02 g/L

October 27th, 2009

6

STACY Experiment with FP (Concentration Worth)*

1 2 3 4

Sm, Cs and Rh concentrations (g/L)

• 500
• 400
• 300
• 200
• 100

Reactivity (cent)

Sm : -3293 ± 40 ¢/(g/L) Rh : -131.4 ± 4.1 ¢/(g/L) Cs : -26.5 ± 1.4 ¢/(g/L)

October 27th, 2009

7

STACY Experiment with FP (Concentration Worth)*

0.005 0.010 0.015 0.020 0.025

Eu concentration (g/L)

• 40
• 30
• 20
• 10

Reactivity (cent)

Eu : -1348 ± 259 ¢/(g/L)

October 27th, 2009

8

STACY Experiment with Gd (Critical Volume)

U ~ 330 (gU/L)

0.00 0.02 0.04 0.06 0.08 0.10 Gd Conc. (g/L) 400 500 600 700 800 900 Critical Solution Level (mm) Water Reflected Core Unreflected Core

October 27th, 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 27th, 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 27th, 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.