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Journal Articles

Introduction to nuclear fuel engineering, 9; LWR fuel behavior

Fuketa, Toyoshi; Nagase, Fumihisa; Sasahara, Akihiro*

Nippon Genshiryoku Gakkai-Shi, 47(2), p.112 - 119, 2005/02

Behavior of LWR fuel during reactivity-initiated accident (RIA) and loss-of-coolant accident (LOCA) is described.

JAEA Reports

Study on the prediction accuracy of nuclide generation and depletion with JENDL

Okumura, Keisuke; Oki, Shigeo*; Yamamoto, Munenari*; Matsumoto, Hideki*; Ando, Yoshihira*; Tsujimoto, Kazufumi; Sasahara, Akihiro*; Katakura, Junichi; Matsumura, Tetsuo*; Aoyama, Takafumi*; et al.

JAERI-Research 2004-025, 154 Pages, 2005/01

JAERI-Research-2004-025.pdf:19.46MB

This report summarizes the activity (FY2000-2003) of Working Group (WG) on Evaluation of Nuclide Generation and Depletion under Subcommittee on Nuclear Fuel Cycle of Japanese Nuclear Data Committee. In the WG, analyses of Post Irradiation Examinations have been carried out for UO$$_{2}$$ and MOX fuels irradiated in PWRs, BWRs and FBRs, and for actinide samples irradiated in fast reactors, by using ORIGEN or more detailed calculation codes with their libraries based on JENDL-3.2, JENDL-3.3 and other foreign nuclear data files. From these results, current prediction accuracy and problems for evaluation of nuclide generation and depletion are discussed. Furthermore, this report covers other products of our activity; development of the ORIGEN libraries for PWR, BWR and FBR based on JENDL-3.3, study on introduction of neutron spectrum index to ORIGEN calculations, and results of questionnaire survey on desirable accuracy of ORIGEN calculations.

JAEA Reports

ORIGEN2 libraries based on JENDL-3.2 for LWR-MOX Fuels

Suyama, Kenya; Onoue, Masaaki*; Matsumoto, Hideki*; Sasahara, Akihiro*; Katakura, Junichi

JAERI-Data/Code 2000-036, 35 Pages, 2000/11

JAERI-Data-Code-2000-036.pdf:1.19MB

no abstracts in English

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