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International case study comparing PSA modeling approaches for nuclear digital I&C – OECD/NEA task DIGMAP

The result's identifiers

  • Result code in IS VaVaI

    <a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F46356088%3A_____%2F23%3AN0000019" target="_blank" >RIV/46356088:_____/23:N0000019 - isvavai.cz</a>

  • Result on the web

    <a href="https://www.sciencedirect.com/science/article/pii/S1738573323003741" target="_blank" >https://www.sciencedirect.com/science/article/pii/S1738573323003741</a>

  • DOI - Digital Object Identifier

    <a href="http://dx.doi.org/10.1016/j.net.2023.08.012" target="_blank" >10.1016/j.net.2023.08.012</a>

Alternative languages

  • Result language

    angličtina

  • Original language name

    International case study comparing PSA modeling approaches for nuclear digital I&C – OECD/NEA task DIGMAP

  • Original language description

    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.

  • Czech name

  • Czech description

Classification

  • Type

    J<sub>imp</sub> - Article in a specialist periodical, which is included in the Web of Science database

  • CEP classification

  • OECD FORD branch

    20305 - Nuclear related engineering; (nuclear physics to be 1.3);

Result continuities

  • Project

  • Continuities

    V - Vyzkumna aktivita podporovana z jinych verejnych zdroju

Others

  • Publication year

    2023

  • Confidentiality

    S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Data specific for result type

  • Name of the periodical

    Nuclear Engineering and Technology

  • ISSN

    1738-5733

  • e-ISSN

  • Volume of the periodical

    55

  • Issue of the periodical within the volume

    12

  • Country of publishing house

    KR - KOREA, REPUBLIC OF

  • Number of pages

    15

  • Pages from-to

    4367 - 4381

  • UT code for WoS article

    001127899500001

  • EID of the result in the Scopus database

    2-s2.0-85171435029