Determination of Probabilistic Inspection Frequency of Structures, Systems and Components of Thai Research Reactor 1-Modification 1 (Trr-1/M1)
Creators
Description
In this work, the probabilistic inspection frequencies of selected Structures, Systems and Components (SSCs) for TRR-1/M1 reactor were determined using Monte Carlo simulations technique. This research assumed that (a) IAEA safety classification is somewhat comparable to the safety integrity level referenced in ISO standards number 13849-1 [5] and (b) the probability of failure of SSCs per hour is constant over time. The failure data was obtained from the IAEA reliability database for research reactor and assumed to be a Chi-Square distribution with degree of freedom equal to number of actual failure components. The results from this research will be used as guidelines for evaluating the TRR-1/M1 operator's inspection and maintenance plan. (author)
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Additional details
Identifiers
Publishing Information
- Imprint Title
- International Conference on Effective Nuclear Regulatory Systems: Sustaining Improvements Globally. Book of Abstracts
- Imprint Pagination
- 106 p.
- Journal Page Range
- p. 62
- Report number
- IAEA-CN--236
Conference
- Title
- Sustaining Improvements Globally
- Acronym
- International Conference on Effective Nuclear Regulatory Systems
- Dates
- 11-15 Apr 2016
- Place
- Vienna (Austria)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 47126680
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; FAILURES; IAEA; INSPECTION; ISO; MONTE CARLO METHOD; PROBABILISTIC ESTIMATION; REACTOR COMPONENTS; REACTOR MAINTENANCE; REACTOR SAFETY; RECOMMENDATIONS; RELIABILITY; TRR-1 REACTOR
- Descriptors DEC
- CALCULATION METHODS; ENRICHED URANIUM REACTORS; INTERNATIONAL ORGANIZATIONS; MAINTENANCE; POOL TYPE REACTORS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SAFETY; SIMULATION; THERMAL REACTORS; TRAINING REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Poster presentation