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Research on the improvement of nuclear safety

Technical Report:

Abstract

To improve the nuclear safety, this project is divided into three areas which are the development of safety analysis technology, the development of severe accident analysis technology and the development of integrated safety assessment technology. 1. The development of safety analysis technology. The present research aims at the development of necessary technologies for nuclear safety analysis in Korea. Establishment of the safety analysis technologies enables to reduce the expenditure both by eliminating excessive conservatisms incorporated in nuclear reactor design and by increasing safety margins in operation. It also contributes to improving plant safety through realistic analyses of the Emergency Operating Procedures (EOP). 2. The development of severe accident analysis technology. By the computer codes (MELCOR and CONTAIN), the in-vessel and the ex-vessel severe accident phenomena are simulated. 3. The development of integrated safety assessment technology. In the development of integrated safety assessment techniques, the included research areas are the improvement of PSA computer codes, the basic study on the methodology for human reliability analysis (HRA) and common cause failure (CCF). For the development of the level 2 PSA computer code, the basic research for the interface between level 1 and 2 PSA, the methodology for the treatment of containment event  More>>
Authors:
Yoo, Keon Joong; Kim, Dong Soo; Kim, Hui Dong; Park, Chang Kyu [1] 
  1. and others; Korea Atomic Energy Res. Inst., Taejon (Korea, Republic of)
Publication Date:
Jun 01, 1993
Product Type:
Technical Report
Report Number:
KAERI/RR-1224/93
Reference Number:
SCA: 210200; 990200; PA: AIX-26:011322; EDB-95:028234; SN: 95001324102
Resource Relation:
Other Information: PBD: Jun 1993
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE; SAFETY; COMPUTER CODES; FUEL-COOLANT INTERACTIONS; HYDRAULICS; LOSS OF COOLANT; PROBABILISTIC ESTIMATION; THERMODYNAMICS; 210200; 990200; POWER REACTORS, NONBREEDING, LIGHT-WATER MODERATED, NONBOILING WATER COOLED; MATHEMATICS AND COMPUTERS
OSTI ID:
10111548
Research Organizations:
Korea Cancer Center Hospital, Seoul (Korea, Republic of)
Country of Origin:
Korea, Republic of
Language:
Korean
Other Identifying Numbers:
Other: ON: DE95612849; TRN: KR9400098011322
Availability:
OSTI; NTIS; INIS
Submitting Site:
KRN
Size:
77 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Yoo, Keon Joong, Kim, Dong Soo, Kim, Hui Dong, and Park, Chang Kyu. Research on the improvement of nuclear safety. Korea, Republic of: N. p., 1993. Web.
Yoo, Keon Joong, Kim, Dong Soo, Kim, Hui Dong, & Park, Chang Kyu. Research on the improvement of nuclear safety. Korea, Republic of.
Yoo, Keon Joong, Kim, Dong Soo, Kim, Hui Dong, and Park, Chang Kyu. 1993. "Research on the improvement of nuclear safety." Korea, Republic of.
@misc{etde_10111548,
title = {Research on the improvement of nuclear safety}
author = {Yoo, Keon Joong, Kim, Dong Soo, Kim, Hui Dong, and Park, Chang Kyu}
abstractNote = {To improve the nuclear safety, this project is divided into three areas which are the development of safety analysis technology, the development of severe accident analysis technology and the development of integrated safety assessment technology. 1. The development of safety analysis technology. The present research aims at the development of necessary technologies for nuclear safety analysis in Korea. Establishment of the safety analysis technologies enables to reduce the expenditure both by eliminating excessive conservatisms incorporated in nuclear reactor design and by increasing safety margins in operation. It also contributes to improving plant safety through realistic analyses of the Emergency Operating Procedures (EOP). 2. The development of severe accident analysis technology. By the computer codes (MELCOR and CONTAIN), the in-vessel and the ex-vessel severe accident phenomena are simulated. 3. The development of integrated safety assessment technology. In the development of integrated safety assessment techniques, the included research areas are the improvement of PSA computer codes, the basic study on the methodology for human reliability analysis (HRA) and common cause failure (CCF). For the development of the level 2 PSA computer code, the basic research for the interface between level 1 and 2 PSA, the methodology for the treatment of containment event tree are performed. Also the new technologies such as artificial intelligence, object-oriented programming techniques are used for the improvement of computer code and the assessment techniques.}
place = {Korea, Republic of}
year = {1993}
month = {Jun}
}