Published 1989
| Version v1
Journal article
Probabilistic risk assessment using event tables and the BNL [Brookhaven National Laboratory] event-tree analyzer
Description
Probabilistic risk analysis (PRA) is being used to study design alternatives for the advanced neutron source research reactor being designed at Oak Ridge National Laboratory for operation in the 1990s. Major communication paths between the designers and the safety analysts are accident discussions supported by event tables, event-tree graphics, and accident sequence probabilities. The BETA code used in conjunction with a word processor provides this linkage. This paper describes the process, features of the BETA, how it works, and some examples of usage
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 60
- Series
- Trans. Am. Nucl. Soc.
- Journal Page Range
- 405-407
- ISSN
- 0003-018X
- CODEN
- TANSA
Conference
- Title
- Winter meeting of the American Nuclear Society (ANS) and nuclear power and technology exhibit.
- Dates
- 26-30 Nov 1989.
- Place
- San Francisco, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22012741
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; B CODES; BNL; COMPUTER GRAPHICS; FAILURE MODE ANALYSIS; ORNL; PRIMARY COOLANT CIRCUITS; PROBABILITY; PROGRAMMING; REACTOR SAFETY; RESEARCH REACTORS; RISK ASSESSMENT; SPECIFICATIONS
- Descriptors DEC
- COMPUTER CODES; COOLING SYSTEMS; NATIONAL ORGANIZATIONS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; US AEC; US DOE; US ERDA; US ORGANIZATIONS
Optional Information
- Secondary number(s)
- CONF-891103--.