Hybrid reliability model for nuclear reactor safety system
- 1. SCK-CEN Belgian Nuclear Research Center, Boeretang 200, B-2400 Mol (Belgium)
- 2. K.U. Leuven, Department of Electrical Engineering (ESAT), Kasteelpark Arenberg 10, B-3001 Heverlee (Belgium)
Description
The dependability of critical safety systems needs to be quantitatively determined in order to verify their effectiveness, e.g. with regard to regulatory requirements. Since modular redundant safety systems are not required for normal operation, their reliability is strongly dependent on periodic inspection. Several modeling methods for the quantitative assessment of dependability are described in the literature, with a broad variation in complexity and modeling power. Static modeling techniques such as fault tree analysis (FTA) or reliability block diagrams (RBD) are not capable of capturing redundancy and repair or test activities. Dynamic state space based models such as continuous time Markov chains (CTMC) are more powerful but often result in very large, intractable models. Moreover, exponentially distributed state residence times are not a correct representation of actual residence times associated with repair activities or periodic inspection. In this study, a hybrid model combines a system level RBD with a CTMC to describe the dynamics. The effects of periodic testing are modeled by redistributing state probabilities at deterministic test times. Applying the method to the primary safety shutdown system of the BR2(Belgian Reactor 2)—nuclear research reactor, resulted in a quantitative as well as a qualitative assessment of its reliability.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.ress.2012.01.004Additional details
Identifiers
- DOI
- 10.1016/j.ress.2012.01.004;
- PII
- S0951-8320(12)00006-3;
Publishing Information
- Journal Title
- Reliability Engineering and System Safety
- Journal Volume
- 101
- Journal Page Range
- p. 35-47
- ISSN
- 0951-8320
- CODEN
- RESSEP
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 43093241
- Subject category
- S42: ENGINEERING;
- Descriptors DEI
- BR-2 REACTOR; DIAGRAMS; ENGINEERED SAFETY SYSTEMS; FAULT TREE ANALYSIS; PERIODICITY; PROBABILITY; REACTOR SHUTDOWN; RELIABILITY; SIMULATION; STEADY-STATE CONDITIONS; TESTING
- Descriptors DEC
- ENRICHED URANIUM REACTORS; INFORMATION; IRRADIATION REACTORS; MATERIALS TESTING REACTORS; REACTORS; SHUTDOWN; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; TANK TYPE REACTORS; THERMAL REACTORS; VARIATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2012 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.