Published June 1990 | Version v1
Journal article

A sensitivity study of support system modeling

Description

In published probabilistic risk assessments, two principal approaches have been used to evaluate the frequencies of accident sequences. The first method uses large fault-tree models of the frontline systems and includes the support systems indirectly through fault-tree linking. The other approach delineates the support systems explicitly in the event trees. The industry degraded core rulemaking individual plant evaluation methodology uses the second approach to avoid the need to use complex computer codes to link large fault trees. In principle, both approaches should yield the same results. In practice, because of the complexities of the systems, approximations have to be made. This paper presents a sensitivity study of two approximations commonly made in the support state approach: (1) modeling on a system level versus train level for support systems and (2) including only the key support systems versus all support systems

Additional details

Publishing Information

Journal Title
Transactions of the American Nuclear Society
Journal Volume
61
Series
Trans. Am. Nucl. Soc.
Journal Page Range
213-214
ISSN
0003-018X
CODEN
TANSA

Conference

Title
American Nuclear Society annual meeting.
Dates
10-14 Jun 1990.
Place
Nashville, TN (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
22034712
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
AVAILABILITY; FAILURE MODE ANALYSIS; FAILURES; FAULT TREE ANALYSIS; FREQUENCY ANALYSIS; NUCLEAR POWER PLANTS; PROBABILITY; REACTOR ACCIDENTS; RISK ASSESSMENT; SENSITIVITY ANALYSIS; SYSTEMS ANALYSIS
Descriptors DEC
ACCIDENTS; NUCLEAR FACILITIES; POWER PLANTS; SYSTEM FAILURE ANALYSIS; THERMAL POWER PLANTS

Optional Information

Secondary number(s)
CONF-900608--.