Evaluating the core damage frequency of a TRIGA research reactor using risk assessment tool software
- 1. School of Engineering, Shiraz University, 71348-51154 Shiraz (Iran, Islamic Republic of)
- 2. Safety Research Center of Shiraz University, 71348-51154 Shiraz (Iran, Islamic Republic of)
Description
Highlights: · In this study, level-I PSA is performed, to reveal and modify the weak points threatening the safe operation of a typical TRIGA reactor. · After identification of the initiating events and developing the appropriate event trees and fault trees, by the risk assessment tool interface, the core damage frequency has been estimated to be 8.368E-6 per year of reactor operation, which meets the IAEA standards. · The results also indicate the significant effects of the common cause failures. - Abstract: After all preventive and mitigative measures considered in the design of a nuclear reactor, the installation still represents a residual risk to the outside world. Probabilistic safety assessment (PSA) is a powerful method to survey the safety of nuclear reactors. In this study the occurrence frequency of different types of core damage states (CDS) which may potentially arise in Tehran Research Reactor (TRR) is evaluated by use of the recently developed risk assessment tool (RAT) software which has been designed and represented in the Safety Research Center of Shiraz University. RAT uses event trees and fault trees to evaluate the total final core damage frequency (CDF) through studying the frequencies of initiation events, and following their consequences has resulted in one type of the CDS. The criterion must be of the order of smaller than 1E-04 through IAEA standards for research reactors (). Results show that the total final CDF for TRR is of the order of 10-6, which meets the criterion of nuclear research reactor.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2011.06.023Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2011.06.023;
- PII
- S0029-5493(11)00506-1;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 241
- Journal Issue
- 8
- Journal Page Range
- p. 2942-2947
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 43048303
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPUTER CODES; DAMAGE; FAILURES; FAULT TREE ANALYSIS; IAEA; PROBABILISTIC ESTIMATION; REACTOR OPERATION; REACTOR SAFETY; RISK ASSESSMENT; SAFETY STANDARDS; TRIGA TYPE REACTORS; UTRR REACTOR
- Descriptors DEC
- CALCULATION METHODS; ENRICHED URANIUM REACTORS; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; INTERNATIONAL ORGANIZATIONS; OPERATION; POOL TYPE REACTORS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SAFETY; SOLID HOMOGENEOUS REACTORS; STANDARDS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2011 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.