You need JavaScript to view this

Nuclear data evaluation and group constant generation for reactor analysis

Technical Report:

Abstract

A one-group cross section data base used by the ORIGEN2 computer code to simulate the depletion, buildup and decay of radionuclides in research reactor was developed. For this, ENDF/B-IV or -V data was processed using the NJOY code system into 69-group data. The burn-up-dependent weighting spectra were calculated with the WIMS-KAERI code, and then the 69-group data were collapsed to one-group using the spectra. The ORIGEN2 depletion calculations for the KMRR fuel were performed using an old PWR and the new data base. By comparing these results to the WIMS-KAERI calculations, it is seen that the results of actinide composition calculated by the ORIGEN2 with the new data base turn out to be in an excellent agreement with the WIMS-KAERI results in the range up to 120 GWD/MTIHM burnup. (Author).
Authors:
Kim, Jung Do; Gil, Choong Sub; Lee, Jong Tai; Hwang, Won Guk [1] 
  1. Korea Atomic Energy Research Inst., Daeduk (Korea, Republic of)
Publication Date:
Dec 01, 1990
Product Type:
Technical Report
Report Number:
KAERI/RR-936/90
Reference Number:
SCA: 220600; PA: AIX-23:022983; SN: 92000682089
Resource Relation:
Other Information: PBD: Dec 1990
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; RESEARCH REACTORS; GROUP CONSTANTS; SELF-POWERED NEUTRON DETECTORS; EVALUATED DATA; ACTINIDES; COMBUSTION; COMPUTER CODES; FISSION PRODUCTS; SPENT FUELS; 220600; RESEARCH, TEST, TRAINING, PRODUCTION, IRRADIATION, MATERIALS TESTING REACTORS
OSTI ID:
10127099
Research Organizations:
Korea Atomic Energy Research Inst., Daeduk (Korea, Republic of)
Country of Origin:
Korea, Republic of
Language:
Korean
Other Identifying Numbers:
Other: ON: DE92619152; TRN: KR9100096022983
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
INIS
Size:
84 p.
Announcement Date:
Jul 04, 2005

Technical Report:

Citation Formats

Kim, Jung Do, Gil, Choong Sub, Lee, Jong Tai, and Hwang, Won Guk. Nuclear data evaluation and group constant generation for reactor analysis. Korea, Republic of: N. p., 1990. Web.
Kim, Jung Do, Gil, Choong Sub, Lee, Jong Tai, & Hwang, Won Guk. Nuclear data evaluation and group constant generation for reactor analysis. Korea, Republic of.
Kim, Jung Do, Gil, Choong Sub, Lee, Jong Tai, and Hwang, Won Guk. 1990. "Nuclear data evaluation and group constant generation for reactor analysis." Korea, Republic of.
@misc{etde_10127099,
title = {Nuclear data evaluation and group constant generation for reactor analysis}
author = {Kim, Jung Do, Gil, Choong Sub, Lee, Jong Tai, and Hwang, Won Guk}
abstractNote = {A one-group cross section data base used by the ORIGEN2 computer code to simulate the depletion, buildup and decay of radionuclides in research reactor was developed. For this, ENDF/B-IV or -V data was processed using the NJOY code system into 69-group data. The burn-up-dependent weighting spectra were calculated with the WIMS-KAERI code, and then the 69-group data were collapsed to one-group using the spectra. The ORIGEN2 depletion calculations for the KMRR fuel were performed using an old PWR and the new data base. By comparing these results to the WIMS-KAERI calculations, it is seen that the results of actinide composition calculated by the ORIGEN2 with the new data base turn out to be in an excellent agreement with the WIMS-KAERI results in the range up to 120 GWD/MTIHM burnup. (Author).}
place = {Korea, Republic of}
year = {1990}
month = {Dec}
}