Proposal of uncertainty analysis methodology for L1PRA using Markov state-transition model

Author:

Haruhara Masanobu1,Muta Hitoshi1,Ohtori Yasuki1,Yamagishi Shohei12,Terayama Shota1

Affiliation:

1. Common Major in Nuclear Energy, Tokyo City University, Setagaya-ku Tokyo, Japan

2. ITOCHU Techno-Solutions Corporation, Minato-ku, Tokyo, Japan

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference19 articles.

1. Nuclear Regulation Authority Operational guidelines for Enhancing the safety of practical Power Reactors Mar. 2020. [in Japanese]

2. U.S.NRC. Dynamic reliability modeling of digital Instrumentation and control systems for Nuclear reactor probabilistic risk assessments (NUREG/CR-6942). U.S.NRC; Oct 2007.

3. U.S.NRC. Traditional probabilistic risk Assessment methods for digital systems (NUREG/CR-6962). U.S.NRC; Oct 2008.

4. U.S.NRC A benchmark implementation of two dynamic methodologies for the reliability modeling of digital Instrumentation and control systems (NUREG/CR-6985) Sept. 2009.

5. U.S.NRC. Development of a statistical testing approach for quantifying safety-related digital system on demand failure probability (NUREG/CR-7234). U.S.NRC; Dec 2017.

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