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Triga mark-II,III reactor safety re-evaluation

Technical Report:

Abstract

In order to revise safety analysis report of old TRIGA reactors, safety re-evaluation of these reactor was started for necessary parts. This report contains the first year results of the project scheduled for two years. The guide lines of safety re-evaluation was made by translating that of nuclear power plant from the view point of TRIGA reactor confirming the basic safety philosophy as much as possible. First of all, sections of reactor history and comparison with similar reactors are made, since the actual operation records, changes, any modification of similar reactors constructed after then, etc., are realistic and valuable data from the safety aspect of old reactor. For the effectiveness of nuclear analysis, a PC based analysis system using WIMS-D/4 and VENTURE was established, and a program for the natural convection cooling analysis of TRIGA reactor was developed. As a result of thermal-hydraulic analysis it was confirmed that the operation limit of fuel temperature set at 650 deg C without any logical reason is very close to the DNB limit. (Author).
Authors:
Jun, Byung Jin; Park, Sang Jun; Kim, Young Joo [1] 
  1. Korea Atomic Energy Research Inst., Daeduk (Korea, Republic of); and others
Publication Date:
Mar 01, 1991
Product Type:
Technical Report
Report Number:
KAERI/RR-983/90
Reference Number:
SCA: 220600; PA: AIX-23:015082; SN: 92000646951
Resource Relation:
Other Information: PBD: Mar 1991
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; TRIGA-2-SEOUL REACTOR; SAFETY; TRIGA-3-SEOUL REACTOR; COMPUTER CODES; EVALUATION; MAINTENANCE; NUCLEAR POWER PLANTS; OPERATION; 220600; RESEARCH, TEST, TRAINING, PRODUCTION, IRRADIATION, MATERIALS TESTING REACTORS
OSTI ID:
10113220
Research Organizations:
Korea Atomic Energy Research Inst., Daeduk (Korea, Republic of)
Country of Origin:
Korea, Republic of
Language:
Korean
Other Identifying Numbers:
Other: ON: DE92615117; TRN: KR9100132015082
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
INIS
Size:
205 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Jun, Byung Jin, Park, Sang Jun, and Kim, Young Joo. Triga mark-II,III reactor safety re-evaluation. Korea, Republic of: N. p., 1991. Web.
Jun, Byung Jin, Park, Sang Jun, & Kim, Young Joo. Triga mark-II,III reactor safety re-evaluation. Korea, Republic of.
Jun, Byung Jin, Park, Sang Jun, and Kim, Young Joo. 1991. "Triga mark-II,III reactor safety re-evaluation." Korea, Republic of.
@misc{etde_10113220,
title = {Triga mark-II,III reactor safety re-evaluation}
author = {Jun, Byung Jin, Park, Sang Jun, and Kim, Young Joo}
abstractNote = {In order to revise safety analysis report of old TRIGA reactors, safety re-evaluation of these reactor was started for necessary parts. This report contains the first year results of the project scheduled for two years. The guide lines of safety re-evaluation was made by translating that of nuclear power plant from the view point of TRIGA reactor confirming the basic safety philosophy as much as possible. First of all, sections of reactor history and comparison with similar reactors are made, since the actual operation records, changes, any modification of similar reactors constructed after then, etc., are realistic and valuable data from the safety aspect of old reactor. For the effectiveness of nuclear analysis, a PC based analysis system using WIMS-D/4 and VENTURE was established, and a program for the natural convection cooling analysis of TRIGA reactor was developed. As a result of thermal-hydraulic analysis it was confirmed that the operation limit of fuel temperature set at 650 deg C without any logical reason is very close to the DNB limit. (Author).}
place = {Korea, Republic of}
year = {1991}
month = {Mar}
}