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

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...

Ausführliche Beschreibung

Gespeichert in:
Bibliographische Detailangaben
Veröffentlicht in:Nuclear engineering and technology 2023, Vol.55 (12), p.4367-4381
Hauptverfasser: Markus Porthin, Sung-Min Shin, Richard Quatrain, Tero Tyrvainen, Jiri Sedlak, Hans Brinkman, Christian Muller, Paolo Picca, Milan Jaros, Venkat Natarajan, Ewgenij Piljugin, Jeanne Demgne
Format: Artikel
Sprache:kor
Online-Zugang:Volltext
Tags: Tag hinzufügen
Keine Tags, Fügen Sie den ersten Tag hinzu!
container_end_page 4381
container_issue 12
container_start_page 4367
container_title Nuclear engineering and technology
container_volume 55
creator Markus Porthin
Sung-Min Shin
Richard Quatrain
Tero Tyrvainen
Jiri Sedlak
Hans Brinkman
Christian Muller
Paolo Picca
Milan Jaros
Venkat Natarajan
Ewgenij Piljugin
Jeanne Demgne
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.
format Article
fullrecord <record><control><sourceid>kisti</sourceid><recordid>TN_cdi_kisti_ndsl_JAKO202311455909502</recordid><sourceformat>XML</sourceformat><sourcesystem>PC</sourcesystem><sourcerecordid>JAKO202311455909502</sourcerecordid><originalsourceid>FETCH-kisti_ndsl_JAKO2023114559095023</originalsourceid><addsrcrecordid>eNqNjEFrwjAYhoNsYNn8D9_F3cqapMF6LLWbdWwVtsNu8tlGF4xJyRcP-_cq-AM8vc8DD--IJULIPJWq-H1gCZ_JIlUzKcdsQmS2WS44z1TBE2YaF3VwGI13aKFD0kDx1P9D548DBuP2sP4u4eh7ba-CwxA8dn-aYOcDuFNnNQbozd7Ey0HzUkEKbV0tXr_qEiLSARbN-2e5fmaPO7SkJ7d9YtO3-qdapgdD0WxcT3azKj9akQnJea7UPJurC9_bnQFgbEXt</addsrcrecordid><sourcetype>Open Access Repository</sourcetype><iscdi>true</iscdi><recordtype>article</recordtype></control><display><type>article</type><title>International case study comparing PSA modeling approaches for nuclear digital I&amp;C - OECD/NEA task DIGMAP</title><source>Directory of Open Journals (DOAJ)</source><source>EZB-FREE-00999 freely available EZB journals</source><source>Alma/SFX Local Collection</source><creator>Markus Porthin ; Sung-Min Shin ; Richard Quatrain ; Tero Tyrvainen ; Jiri Sedlak ; Hans Brinkman ; Christian Muller ; Paolo Picca ; Milan Jaros ; Venkat Natarajan ; Ewgenij Piljugin ; Jeanne Demgne</creator><creatorcontrib>Markus Porthin ; Sung-Min Shin ; Richard Quatrain ; Tero Tyrvainen ; Jiri Sedlak ; Hans Brinkman ; Christian Muller ; Paolo Picca ; Milan Jaros ; Venkat Natarajan ; Ewgenij Piljugin ; Jeanne Demgne</creatorcontrib><description><![CDATA[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.]]></description><identifier>ISSN: 1738-5733</identifier><identifier>EISSN: 2234-358X</identifier><language>kor</language><ispartof>Nuclear engineering and technology, 2023, Vol.55 (12), p.4367-4381</ispartof><lds50>peer_reviewed</lds50><oa>free_for_read</oa><woscitedreferencessubscribed>false</woscitedreferencessubscribed></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><link.rule.ids>230,314,780,784,885,4022</link.rule.ids></links><search><creatorcontrib>Markus Porthin</creatorcontrib><creatorcontrib>Sung-Min Shin</creatorcontrib><creatorcontrib>Richard Quatrain</creatorcontrib><creatorcontrib>Tero Tyrvainen</creatorcontrib><creatorcontrib>Jiri Sedlak</creatorcontrib><creatorcontrib>Hans Brinkman</creatorcontrib><creatorcontrib>Christian Muller</creatorcontrib><creatorcontrib>Paolo Picca</creatorcontrib><creatorcontrib>Milan Jaros</creatorcontrib><creatorcontrib>Venkat Natarajan</creatorcontrib><creatorcontrib>Ewgenij Piljugin</creatorcontrib><creatorcontrib>Jeanne Demgne</creatorcontrib><title>International case study comparing PSA modeling approaches for nuclear digital I&amp;C - OECD/NEA task DIGMAP</title><title>Nuclear engineering and technology</title><addtitle>Nuclear engineering and technology : an international journal of the Korean Nuclear Society</addtitle><description><![CDATA[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.]]></description><issn>1738-5733</issn><issn>2234-358X</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2023</creationdate><recordtype>article</recordtype><sourceid>JDI</sourceid><recordid>eNqNjEFrwjAYhoNsYNn8D9_F3cqapMF6LLWbdWwVtsNu8tlGF4xJyRcP-_cq-AM8vc8DD--IJULIPJWq-H1gCZ_JIlUzKcdsQmS2WS44z1TBE2YaF3VwGI13aKFD0kDx1P9D548DBuP2sP4u4eh7ba-CwxA8dn-aYOcDuFNnNQbozd7Ey0HzUkEKbV0tXr_qEiLSARbN-2e5fmaPO7SkJ7d9YtO3-qdapgdD0WxcT3azKj9akQnJea7UPJurC9_bnQFgbEXt</recordid><startdate>2023</startdate><enddate>2023</enddate><creator>Markus Porthin</creator><creator>Sung-Min Shin</creator><creator>Richard Quatrain</creator><creator>Tero Tyrvainen</creator><creator>Jiri Sedlak</creator><creator>Hans Brinkman</creator><creator>Christian Muller</creator><creator>Paolo Picca</creator><creator>Milan Jaros</creator><creator>Venkat Natarajan</creator><creator>Ewgenij Piljugin</creator><creator>Jeanne Demgne</creator><scope>JDI</scope></search><sort><creationdate>2023</creationdate><title>International case study comparing PSA modeling approaches for nuclear digital I&amp;C - OECD/NEA task DIGMAP</title><author>Markus Porthin ; Sung-Min Shin ; Richard Quatrain ; Tero Tyrvainen ; Jiri Sedlak ; Hans Brinkman ; Christian Muller ; Paolo Picca ; Milan Jaros ; Venkat Natarajan ; Ewgenij Piljugin ; Jeanne Demgne</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-kisti_ndsl_JAKO2023114559095023</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>kor</language><creationdate>2023</creationdate><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Markus Porthin</creatorcontrib><creatorcontrib>Sung-Min Shin</creatorcontrib><creatorcontrib>Richard Quatrain</creatorcontrib><creatorcontrib>Tero Tyrvainen</creatorcontrib><creatorcontrib>Jiri Sedlak</creatorcontrib><creatorcontrib>Hans Brinkman</creatorcontrib><creatorcontrib>Christian Muller</creatorcontrib><creatorcontrib>Paolo Picca</creatorcontrib><creatorcontrib>Milan Jaros</creatorcontrib><creatorcontrib>Venkat Natarajan</creatorcontrib><creatorcontrib>Ewgenij Piljugin</creatorcontrib><creatorcontrib>Jeanne Demgne</creatorcontrib><collection>KoreaScience</collection><jtitle>Nuclear engineering and technology</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Markus Porthin</au><au>Sung-Min Shin</au><au>Richard Quatrain</au><au>Tero Tyrvainen</au><au>Jiri Sedlak</au><au>Hans Brinkman</au><au>Christian Muller</au><au>Paolo Picca</au><au>Milan Jaros</au><au>Venkat Natarajan</au><au>Ewgenij Piljugin</au><au>Jeanne Demgne</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>International case study comparing PSA modeling approaches for nuclear digital I&amp;C - OECD/NEA task DIGMAP</atitle><jtitle>Nuclear engineering and technology</jtitle><addtitle>Nuclear engineering and technology : an international journal of the Korean Nuclear Society</addtitle><date>2023</date><risdate>2023</risdate><volume>55</volume><issue>12</issue><spage>4367</spage><epage>4381</epage><pages>4367-4381</pages><issn>1738-5733</issn><eissn>2234-358X</eissn><abstract><![CDATA[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.]]></abstract><oa>free_for_read</oa></addata></record>
fulltext fulltext
identifier ISSN: 1738-5733
ispartof Nuclear engineering and technology, 2023, Vol.55 (12), p.4367-4381
issn 1738-5733
2234-358X
language kor
recordid cdi_kisti_ndsl_JAKO202311455909502
source Directory of Open Journals (DOAJ); EZB-FREE-00999 freely available EZB journals; Alma/SFX Local Collection
title International case study comparing PSA modeling approaches for nuclear digital I&C - OECD/NEA task DIGMAP
url https://sfx.bib-bvb.de/sfx_tum?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&ctx_tim=2025-01-10T03%3A06%3A45IST&url_ver=Z39.88-2004&url_ctx_fmt=infofi/fmt:kev:mtx:ctx&rfr_id=info:sid/primo.exlibrisgroup.com:primo3-Article-kisti&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.atitle=International%20case%20study%20comparing%20PSA%20modeling%20approaches%20for%20nuclear%20digital%20I&C%20-%20OECD/NEA%20task%20DIGMAP&rft.jtitle=Nuclear%20engineering%20and%20technology&rft.au=Markus%20Porthin&rft.date=2023&rft.volume=55&rft.issue=12&rft.spage=4367&rft.epage=4381&rft.pages=4367-4381&rft.issn=1738-5733&rft.eissn=2234-358X&rft_id=info:doi/&rft_dat=%3Ckisti%3EJAKO202311455909502%3C/kisti%3E%3Curl%3E%3C/url%3E&disable_directlink=true&sfx.directlink=off&sfx.report_link=0&rft_id=info:oai/&rft_id=info:pmid/&rfr_iscdi=true