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Development of accident management technology and computer codes -A study for nuclear safety improvement-

Technical Report:

Abstract

We have surveyed new technologies and research results for the accident management of nuclear power plants. And, based on the concept of using the existing plant capabilities for accident management, both in-vessel and ex-vessel strategies were identified and analyzed. When assessing accident management strategies, their effectiveness, adverse effects, and their feasibility must be considered. We have developed a framework for assessing the strategies with these factors in mind. We have applied the developed framework to assessing the strategies, including the likelihood that the operator correctly diagnoses the situation and successfully implements the strategies. Finally, the cavity flooding strategy was assessed by applying it to the station blackout sequence, which have been identified as one of the major contributors to risk at the reference plant. The thermohydraulic analyses with sensitivity calculations have been performed using MAAP 4 computer code. (Author).
Authors:
Park, Chang Kyu; Jae, Moo Sung; Jo, Young Gyun; Park, Rae Jun; Kim, Jae Hwan; Ha, Jae Ju; Kang, Dae Il; Choi, Sun Young; Kim, Si Hwan [1] 
  1. Korea Atomic Energy Res. Inst., Taejon (Korea, Republic of)
Publication Date:
Jul 01, 1994
Product Type:
Technical Report
Report Number:
KAERI/RR-1330/93
Reference Number:
SCA: 990200; 990100; PA: AIX-26:012082; EDB-95:033493; SN: 95001324577
Resource Relation:
Other Information: PBD: Jul 1994
Subject:
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE; SAFETY; ACCIDENTS; COMPUTER CODES; EMERGENCY PLANS; HUMAN FACTORS; PROBABILISTIC ESTIMATION; RISK ASSESSMENT; 990200; 990100; MATHEMATICS AND COMPUTERS; MANAGEMENT
OSTI ID:
10112269
Research Organizations:
Korea Cancer Center Hospital, Seoul (Korea, Republic of)
Country of Origin:
Korea, Republic of
Language:
Korean
Other Identifying Numbers:
Other: ON: DE95613322; TRN: KR9400168012082
Availability:
OSTI; NTIS; INIS
Submitting Site:
KRN
Size:
230 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Park, Chang Kyu, Jae, Moo Sung, Jo, Young Gyun, Park, Rae Jun, Kim, Jae Hwan, Ha, Jae Ju, Kang, Dae Il, Choi, Sun Young, and Kim, Si Hwan. Development of accident management technology and computer codes -A study for nuclear safety improvement-. Korea, Republic of: N. p., 1994. Web.
Park, Chang Kyu, Jae, Moo Sung, Jo, Young Gyun, Park, Rae Jun, Kim, Jae Hwan, Ha, Jae Ju, Kang, Dae Il, Choi, Sun Young, & Kim, Si Hwan. Development of accident management technology and computer codes -A study for nuclear safety improvement-. Korea, Republic of.
Park, Chang Kyu, Jae, Moo Sung, Jo, Young Gyun, Park, Rae Jun, Kim, Jae Hwan, Ha, Jae Ju, Kang, Dae Il, Choi, Sun Young, and Kim, Si Hwan. 1994. "Development of accident management technology and computer codes -A study for nuclear safety improvement-." Korea, Republic of.
@misc{etde_10112269,
title = {Development of accident management technology and computer codes -A study for nuclear safety improvement-}
author = {Park, Chang Kyu, Jae, Moo Sung, Jo, Young Gyun, Park, Rae Jun, Kim, Jae Hwan, Ha, Jae Ju, Kang, Dae Il, Choi, Sun Young, and Kim, Si Hwan}
abstractNote = {We have surveyed new technologies and research results for the accident management of nuclear power plants. And, based on the concept of using the existing plant capabilities for accident management, both in-vessel and ex-vessel strategies were identified and analyzed. When assessing accident management strategies, their effectiveness, adverse effects, and their feasibility must be considered. We have developed a framework for assessing the strategies with these factors in mind. We have applied the developed framework to assessing the strategies, including the likelihood that the operator correctly diagnoses the situation and successfully implements the strategies. Finally, the cavity flooding strategy was assessed by applying it to the station blackout sequence, which have been identified as one of the major contributors to risk at the reference plant. The thermohydraulic analyses with sensitivity calculations have been performed using MAAP 4 computer code. (Author).}
place = {Korea, Republic of}
year = {1994}
month = {Jul}
}