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 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.

Implementation of emergency system for radioactive source term estimation on global meta-computing environment and its real-time visualization

Muramatsu, Kazuhiro; Imamura, Toshiyuki; Kitabata, Hideyuki; Kaneko, Isamu; Takemiya, Hiroshi*; Hasegawa, Yukihiro*; Yamagishi, Nobuhiro*; Hirayama, Toshio

Keisan Kogaku Koenkai Rombunshu, 6(1), p.241 - 244, 2001/05

no abstracts in English

Plutonium solution storage vessel with fixed neutron absorber

; Kaneko, Toshiyuki*; Yamamoto, Toshihiro; Miyoshi, Yoshinori

Proceedings of 6th International Conference on Nuclear Criticality Safety (ICNC '99), 1, p.252 - 261, 1999/00

no abstracts in English

Validation of SWAT for burnup credit problems by analysis of pie of 1717 PWR fuel assembly

Suyama, Kenya; Nakahara, Yoshinori; Kaneko, Toshiyuki*;

Proc. of PATRAM'98, 1, p.239 - 244, 1998/00

no abstracts in English

Burnup code for fuel assembly by Monte Carlo code; MKENO-BURN

Naito, Yoshitaka; Suyama, Kenya; Masukawa, Fumihiro; Matsumoto, Kiyoshi; Kurosawa, Masayoshi;

JAERI-Data/Code 96-037, 70 Pages, 1996/12

JAERI-Data-Code-96-037.pdf:1.68MB

no abstracts in English

Isotopic composition of spent fuels for criticality safety evaluation and isotopic composition database (SFCOMPO)

Kurosawa, Masayoshi; Naito, Yoshitaka;

ICNC 95: 5th Int. Conf. on Nuclear Criticality Safety, Vol. I, 0, p.2.11 - 2.15, 1995/00

no abstracts in English

Data book of the isotopic composition of spent fuel in light water reactors

Naito, Yoshitaka; Kurosawa, Masayoshi;

JAERI-M 94-034, 225 Pages, 1994/03

JAERI-M-94-034.pdf:5.59MB

no abstracts in English

Reduction of nitrogen oxides by gamma-irradiated hemoprotein, Part II; Reduction of nitrite by immobilized gamma-irradiated hemoprotein

; ; ; ; ; ; ; Kume, Tamikazu

Shokuhin Shosha, 29(1-2), p.16 - 20, 1994/00

no abstracts in English

Installation of Monte Carlo neutron and photon transport code system MCNP-4; Improvements of graphic functions and cross section library for Sun work stations

; Sasaki, Mikio*; ;

JAERI-M 93-050, 72 Pages, 1993/03

JAERI-M-93-050.pdf:1.62MB

no abstracts in English

The preliminary edition of nuclear criticality safety handbook of Japan, 4; Development of a computer code for analysing nuclear criticality safety on array system

Kaneko, Yoshiyuki*; Naito, Yoshitaka

Proc.Int.Seminar on Nuclear Criticality Safety, p.150 - 155, 1987/00

no abstracts in English