Published October 2010 | Version v1
Journal article

Application of the CFAST zone model to the Fire PSA

  • 1. Korea Atomic Energy Research Institute, P.O. Box 105, Yuseong, Daejeon (Korea, Republic of)
  • 2. Kwangwoon University, 447-1, Nowon-goo, Seoul (Korea, Republic of)

Description

The integrity of the cables located in the target room is very important in the Fire PSA, because the CDF and CCDP are changed according to the results of a cable integrity that depends on the surrounding gas temperature. The conservative assumptions used in the Fire PSA typically specify that all of the equipment and cables of a room would fail when a fire happens in the room. But the realistic assessment of a fire risk by using a fire simulation tool has become necessary in the Fire PSA as described in the ANS Fire PRA Standard. This paper evaluates the cable integrity of eight pump rooms in the nuclear power plant by using the CFAST zone fire model. The upper layer gas temperature of each room is estimated, and an analysis based on the results of model simulations is used to judge the cable integrity. According to the analysis results, the integrity of the cable located in the upper layer in the pump rooms is maintained without any thermal damage, and the CCDP is reduced to about the half of the original CCDP. A fire safety assessment for dominant pump rooms by using a fire modeling tool is seen capable of evaluating the consequences of a fire scenario, of reducing the uncertainty, and of developing a more realistic Fire PSA model. It is considered that the fire modeling can satisfy the requirements of the ANS Fire PRA standard related to a fire modeling, and improve the quality of the Fire PSA.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2010.04.035

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2010.04.035;
PII
S0029-5493(10)00319-5;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
240
Journal Issue
10
Journal Page Range
p. 3571-3576
ISSN
0029-5493
CODEN
NEDEAU

Conference

Title
4. international topical meeting on high temperature reactor technology
Acronym
HTR 2008
Dates
28 Sep - 1 Oct 2008
Place
Washington, DC (United States)

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
42013371
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
AUXILIARY WATER SYSTEMS; CABLES; DAMAGE; FIRE HAZARDS; FIRES; NUCLEAR POWER PLANTS; PROBABILISTIC ESTIMATION; PUMPS; REACTOR CORE DISRUPTION; RISK ASSESSMENT; SIMULATION
Descriptors DEC
ACCIDENTS; AUXILIARY SYSTEMS; CALCULATION METHODS; EQUIPMENT; HAZARDS; NUCLEAR FACILITIES; POWER PLANTS; REACTOR ACCIDENTS; THERMAL POWER PLANTS

Optional Information

Copyright
Copyright (c) 2010 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.