Defining accident sequences for conducting probabilistic risk assessments
Description
A major portion of any PRA activity is devoted to the identification of potential accident sequences which could lead to radiological releases. A systematic application of acceptable methods and techniques is desirable. Event tree and fault tree analysis form the basis for plant/system modeling. Consensus approaches for acquisition of information, model development, assumptions, constraints, inclusion of common cause events, interrelationships of event trees and fault trees, accuracy, completeness and manner of documentation are presented. Alternative methods which may be used or directed toward a specialized purpose are also of interest. Particular emphasis is placed on defining in practical terms the specific tasks of accident sequence definition and what is required, why it is necessary and how each task relates to the overall risk assessment process
Additional details
Publishing Information
- Publisher
- American Nuclear Society, Inc.
- Imprint Place
- La Grange Park, IL
- Imprint Title
- Probabilistic risk assessment
- Journal Page Range
- p. 1511-1519.
Conference
- Title
- ANS/ENS topical meeting on probabilistic risk assessment.
- Dates
- 20-24 Sep 1981.
- Place
- Port Chester, NY (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 15014048
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALGORITHMS; COMPUTERIZED SIMULATION; FAULT TREE ANALYSIS; NUCLEAR POWER PLANTS; PROBABILITY; RADIATION HAZARDS; REACTOR ACCIDENTS; RISK ANALYSIS
- Descriptors DEC
- ACCIDENTS; HAZARDS; HEALTH HAZARDS; NUCLEAR FACILITIES; POWER PLANTS; SIMULATION; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL POWER PLANTS