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논문 기본 정보

자료유형
학술저널
저자정보
Porthin Markus (Paul Scherrer Institut (PSI)) Sedlak Jiri (ÚJV Rez) Müller Christian (Gesellschaft für Anlagen- und Reaktorsicherheit (GRS)) Picca Paolo Jaros Milan (Office for Nuclear Regulation (ONR), Merton Road) Natarajan Venkat (ÚJV ˇReˇz) Piljugin Ewgenij (NRG) Demgné Jeanne (EDF) 신성민 (한국원자력연구원) Quatrain Richard (EDF R&D, EDF Lab Paris-Saclay) Tyrväinen Tero (VTT Technical Research Centre of Finland Ltd (VTT)) Sedlak Jiri (ÚJV Řež, a. s.) Brinkman Hans (NRG) Müller Christian (Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH) Picca Paolo (Office for Nuclear Regulation) Jaros Milan (ÚJV Řež, a. s.) Natarajan Venkat (NRG) Piljugin Ewgenij (Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH) Demgné Jeanne (EDF R&D, EDF Lab Paris-Saclay)
저널정보
한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology Vol.55 No.12
발행연도
2023.12
수록면
4,367 - 4,381 (15page)
DOI
10.1016/j.net.2023.08.012

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Nuclear power plants are increasingly being equipped with digital I&C systems. Although some probabilistic safety assessment (PSA) models for the digital I&C of nuclear power plants have been constructed, there is currently no specific internationally agreed guidance for their modeling. This paper presents an initiative by the OECD Nuclear Energy Agency called “Digital I&C PSA – Comparative application of DIGital I&C Modelling Approaches for PSA (DIGMAP)”, which aimed to advance the field towards practical and defendable modeling principles. The task, carried out in 2017–2021, used a simplified description of a plant focusing on the digital I&C systems important to safety, for which the participating organizations independently developed their own PSA models. Through comparison of the PSA models, sensitivity analyses as well as observations throughout the whole activity, both qualitative and quantitative lessons were learned. These include insights on failure behavior of digital I&C systems, experience from models with different levels of abstraction, benefits from benchmarking as well as major contributors to the core damage frequency and those with minor effect. The study also highlighted the challenges with modeling of large common cause component groups and the difficulties associated with estimation of key software and common cause failure parameters

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