TAILIEUCHUNG - AIMS-MUPSA software package for multi-unit PSA

This paper deals with the methodology and software to quantify a PSA scenarios for a multi-unit site. Two approaches are developed to quantify a multi-unit PSA. One is to use a minimal cut set approach, and the other is to use a Monte Carlo approach. | Nuclear Engineering and Technology 50 2018 1255 1265 ELSEVIER Contents lists available at ScienceDirect Nuclear Engineering and Technology journal homepage locate net nuclear ENGINEERING AND TECHNOLOGY Topical Issue Article AIMS-MUPSA software package for multi-unit PSA Sang Hoon Han a Kyemin Oh b Ho-Gon Lim a Joon-Eon Yang a Check for updates a Risk Environment Safety Research Division Korea Atomic Energy Research Institute 1045 Daedeokdaero Yuseong-gu Daejeon 305-353 Republic of Korea b KHNP Central Research Institute Daejeon 34101 Republic of Korea ARTICLE INFO ABSTRACT Article history Received 21 September 2017 Received in revised form 24 April 2018 Accepted 11 June 2018 Available online 15 June 2018 The need for a PSA Probabilistic Safety Assessment for a multi-unit at a site is growing after the Fukushima accident. Many countries have been studying issues regarding a multi-unit PSA. One of these issues is the problem of many combinations of accident sequences in a multi-unit PSA. This paper deals with the methodology and software to quantify a PSA scenarios for a multi-unit site. Two approaches are developed to quantify a multi-unit PSA. One is to use a minimal cut set approach and the other is to use a Monte Carlo approach. Keywords Multi-unit PSA Multi-unit PSA scenario Minimal cut set approach Monte Carlo approach PSA software 2018 Korean Nuclear Society Published by Elsevier Korea LLC. This is an open access article under the CC BY-NC-ND license http licenses by-nc-nd . 1. Introduction Many nuclear power plants are composed of several nuclear power plants at a site. PSAs Probabilistic safety assessment of multi-unit sites have been piloted since the early 1980s such as the Seabrook PSA 1 . Since 2000 it has become necessary to examine the suitability of the current safety health objectives with regard to SMR Small modular reactor licensing which is composed of multiple reactors. The Fukushima accident also .

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• Nuclear engineering and technology
• AIMS MUPSA software package for multi unit PSA
• AIMS MUPSA software package
• Multi unit PSA scenario
• Minimal cut set approach
• Monte Carlo approach
• Integral nuclear data validation
• Experimental spent nuclear fuel compositions
• Economic Co operation and Development
• Nuclear Energy Agency
• Nuclear Criticality Safety
• Expanded spent fuel isotopic compositions
• Nuclear reactor vessel water level prediction during severe accidents
• Deep neural networks
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• Maintain nuclear reactor integrity
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• The Nuclear Engineering and Technolog
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