Refine your search:     
Report No.
 - 
Search Results: Records 1-2 displayed on this page of 2
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Current status of spent fuel isotopic composition database SFCOMPO and related technical development by JAEA

Suyama, Kenya; Okuno, Hiroshi; Uchiyama, Gunzo

Need for Post Irradiation Experiments to Validate Fuel Depletion Calculation Methodologies, p.151 - 156, 2006/12

In the field of criticality safety evaluation of spent fuels, Japan Atomic Energy Agency (former Japan Atomic Energy Research Institute, JAERI) has carried out continuous research and development. The effort includes obtaining isotopic composition data of spent nuclear fuels by the post irradiation examinations (PIE) for spent fuels irradiated in light water reactors and developing burnup calculation code system SWAT and new libraries for ORIGEN2 code adopting latest nuclear data libraries. JAERI had developed isotopic composition database SFCOMPO. This report describes current status of SFCOMPO and a result of technical developments of burnup credit in JAEA, i.e. re-evaluation of burnup values of PIE data taken at JAERI.

Journal Articles

Current status and potential needs of burn-up credit in Japan

Suyama, Kenya; Okuno, Hiroshi; Uchiyama, Gunzo; Yamamoto, Toru*

Need for Post Irradiation Experiments to Validate Fuel Depletion Calculation Methodologies, p.31 - 34, 2006/12

In Japan, burnup credit (BUC) has already been introduced into the criticality safety evaluation of Spent Nuclear Fuel (SNF) receiving pools and dissolver at Rokkasho Reprocessing Plant (RRP). BUC in other fuel cycle facilities including SNF transport is not considered. This is because the pressure of accumulation of SNF in Japan is decreased for a while since (1) the operation of spent fuel storage pools in RRP and (2) proposal of construction of an interim storage facility using dry-type metal casks by Recyclable-Fuel Storage Company (RFS) in Aomori. However, potential demands for adoption of BUC and improvement of related techniques have been still high. The technical development related to BUC is in progress continuously in the field of burnup analysis as post irradiation examinations (PIE) and reactor physics experiments. This concludes that BUC is an attractive concept and further adoption in spent fuel management process is expected in Japan.

2 (Records 1-2 displayed on this page)
  • 1