Comparative application of digital I&C modeling approaches for PSA

Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F46356088%3A_____%2F19%3AN0000031" target="_blank" >RIV/46356088:_____/19:N0000031 - isvavai.cz</a>
Result on the web
<a href="http://www.ans.org/store/item-700429/" target="_blank" >http://www.ans.org/store/item-700429/</a>
DOI - Digital Object Identifier
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Result language
angličtina
Original language name
Comparative application of digital I&C modeling approaches for PSA
Original language description
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.
Czech name
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Czech description
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Type
D - Article in proceedings
CEP classification
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OECD FORD branch
20305 - Nuclear related engineering; (nuclear physics to be 1.3);

Publication year
2019
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Article name in the collection
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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Number of pages
9
Pages from-to
321-329
Publisher name
American Nuclear Society
Place of publication
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Event location
Charleston, USA
Event date
Apr 28, 2019
Type of event by nationality
WRD - Celosvětová akce
UT code for WoS article
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