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
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Czech description
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Classification
Type
J<sub>imp</sub> - Article in a specialist periodical, which is included in the Web of Science database
CEP classification
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OECD FORD branch
20305 - Nuclear related engineering; (nuclear physics to be 1.3);
Result continuities
Project
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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
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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