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Post accident core damage assessment methodology and code

Technical Report:

Abstract

Post accident core damage assessment methodology is a part of nuclear power plant emergency plan. It is used to assess core damage states and extents after an accident. Core damage states include no core damage, fuel clad failure, fuel overheat and fuel melt. The methodology consists of detailed assessment based on sampling system and primary assessment based on on-line monitoring system. A few aspects in post accident core damage assessment methodology developed by Westinghouse in 1984 were improved, such as introducing a modification factor related to fuel burnup and some other factors related to fission product retention on the surfaces of RCS (reactor coolant system) using research results about severe accidents. The methodology and the developed computer code have already been used in Qinshan NPP (nuclear power plant) and can also be used in other PWR (pressurized water reactor) NPPs.
Authors:
Zhongliang, He; Shu, Zhao [1] 
  1. Shanghai Nuclear Engineering Research and Development Inst., SH (China)
Publication Date:
Jun 01, 1993
Product Type:
Technical Report
Report Number:
CNIC-00769; SNERDI-0021.
Reference Number:
SCA: 210200; PA: AIX-26:011318; EDB-95:028204; SN: 95001324100
Resource Relation:
Other Information: PBD: Jun 1993
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; PWR TYPE REACTORS; REACTOR CORE DISRUPTION; SAFETY; C CODES; EMERGENCY PLANS; EVALUATION; FISSION PRODUCT RELEASE; FUEL ELEMENT FAILURE; FUEL ELEMENTS; MELTING; NUCLEAR POWER PLANTS; ON-LINE MEASUREMENT SYSTEMS; 210200; POWER REACTORS, NONBREEDING, LIGHT-WATER MODERATED, NONBOILING WATER COOLED
OSTI ID:
10111542
Research Organizations:
China Nuclear Information Centre, Beijing, BJ (China)
Country of Origin:
China
Language:
Chinese
Other Identifying Numbers:
Other: ON: DE95612847; ISBN 7-5022-0949-2; TRN: CN9402479011318
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
INIS
Size:
15 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Zhongliang, He, and Shu, Zhao. Post accident core damage assessment methodology and code. China: N. p., 1993. Web.
Zhongliang, He, & Shu, Zhao. Post accident core damage assessment methodology and code. China.
Zhongliang, He, and Shu, Zhao. 1993. "Post accident core damage assessment methodology and code." China.
@misc{etde_10111542,
title = {Post accident core damage assessment methodology and code}
author = {Zhongliang, He, and Shu, Zhao}
abstractNote = {Post accident core damage assessment methodology is a part of nuclear power plant emergency plan. It is used to assess core damage states and extents after an accident. Core damage states include no core damage, fuel clad failure, fuel overheat and fuel melt. The methodology consists of detailed assessment based on sampling system and primary assessment based on on-line monitoring system. A few aspects in post accident core damage assessment methodology developed by Westinghouse in 1984 were improved, such as introducing a modification factor related to fuel burnup and some other factors related to fission product retention on the surfaces of RCS (reactor coolant system) using research results about severe accidents. The methodology and the developed computer code have already been used in Qinshan NPP (nuclear power plant) and can also be used in other PWR (pressurized water reactor) NPPs.}
place = {China}
year = {1993}
month = {Jun}
}