Comparative application of digital I&C modeling approaches for PSA

Kód výsledku v IS VaVaI

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Výsledek na webu

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DOI - Digital Object Identifier

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Jazyk výsledku

angličtina

Název v původním jazyce

Comparative application of digital I&C modeling approaches for PSA

Popis výsledku v původním jazyce

Newly built and modernized older nuclear power plants are equipped with digital I&C systems. However, currently there is no specific guidance internationally agreed for modeling of digital I&C systems in PSA. Thus, the OECD Nuclear Energy Agency (NEA) Committee on the Safety of Nuclear Installations (CSNI) Working Group on Risk Assessment (WGRISK) initiated a task called “Digital I&C PSA - Comparative application of DIGital I&C Modeling Approaches for PSA” (DIGMAP) in July 2017. The objective of the task is to compare different modeling approaches and identify possible methods and issues for further development. A simplified boiling water reactor design equipped with digital features is used as a common reference plant for the task. Each participating country develops its own PSA model based on the plant description. Through comparison, different approaches to account for e.g. software reliability, fault-tolerant techniques, and network communication in the PSA will be explored. Nine countries are currently participating in the task. The planned duration for the task is 2017-2020. This paper describes the efforts done so far and presents preliminary results and insights.

Název v anglickém jazyce

Comparative application of digital I&C modeling approaches for PSA

Popis výsledku anglicky

Newly built and modernized older nuclear power plants are equipped with digital I&C systems. However, currently there is no specific guidance internationally agreed for modeling of digital I&C systems in PSA. Thus, the OECD Nuclear Energy Agency (NEA) Committee on the Safety of Nuclear Installations (CSNI) Working Group on Risk Assessment (WGRISK) initiated a task called “Digital I&C PSA - Comparative application of DIGital I&C Modeling Approaches for PSA” (DIGMAP) in July 2017. The objective of the task is to compare different modeling approaches and identify possible methods and issues for further development. A simplified boiling water reactor design equipped with digital features is used as a common reference plant for the task. Each participating country develops its own PSA model based on the plant description. Through comparison, different approaches to account for e.g. software reliability, fault-tolerant techniques, and network communication in the PSA will be explored. Nine countries are currently participating in the task. The planned duration for the task is 2017-2020. This paper describes the efforts done so far and presents preliminary results and insights.

Druh

D - Stať ve sborníku

CEP obor

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OECD FORD obor

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

Projekt

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Návaznosti

V - Vyzkumna aktivita podporovana z jinych verejnych zdroju

Rok uplatnění

2019

Kód důvěrnosti údajů

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

Název statě ve sborníku

International Topical Meeting on Probabilistic Safety Assessment and Analysis (PSA 2019)

ISBN

978-0-89448-763-7

ISSN

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e-ISSN

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Počet stran výsledku

9

Strana od-do

321-329

Název nakladatele

American Nuclear Society

Místo vydání

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Místo konání akce

Charleston, USA

Datum konání akce

28. 4. 2019

Typ akce podle státní příslušnosti

WRD - Celosvětová akce

Kód UT WoS článku

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