Proposal of PRA Methodology Considering State Transitions and Time-Dependent Failure Rates of Components

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  • MUTA Hitoshi
    Department of Nuclear Safety Engineering, Faculty of Engineering, Tokyo City University
  • FURUYA Osamu
    Department of Nuclear Safety Engineering, Faculty of Engineering, Tokyo City University
  • MURAMATSU Ken
    Department of Nuclear Safety Engineering, Faculty of Engineering, Tokyo City University

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  • 機器の状態遷移および経時的変化の影響を考慮したPRA手法の提案
  • キキ ノ ジョウタイ センイ オヨビ ケイジテキ ヘンカ ノ エイキョウ オ コウリョ シタ PRA シュホウ ノ テイアン

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One of the most important issues of the current PRA methodology is the precise modeling of dynamic changes such as state transitions among several states including fault(s) or maintenance of the nuclear facility, safety-related systems or components by fault-tree analysis and event-tree analysis. Moreover, though safety-related systems are usually in the stand-by state during normal operating conditions of a nuclear power plant, modeling of the dynamic changes in safety functions, along with changes in component failure rates due to the aging effect in the stand-by state or continuous/intermittent effects originating from external hazards, is also carried out under the same situation. On the basis of the background described above, the authors proposed a reliability analysis methodology of using the Markov state transition model applied to the digital reactor protection system of an ABWR plant, and demonstrated the applicability of the developed methodology using the component failure modes discussed in DIGREL, the task group of WGRisk belonging to OECD/NEA/CSNI. These studies showed that the PRA methodology including the state transition model can consider state transitions of components and time-dependent changes in component failure rates, and the relationship between this methodology and minimal cut sets for calculating the core damage frequency was also clarified.

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