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Comparative application of digital I&C modeling approaches for PSA

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Názov: Comparative application of digital I&C modeling approaches for PSA
Autori: Porthin, Markus, Shin, Sung Min, Tyrväinen, Tero, Mueller, Christian, Piljugin, Ewgenij, Stiller, Jan, Quatrain, Richard, Granseigne, Leo, Brinkman, Hans, Picca, Paolo, Gordon, Joshua, Sedlak, Jiri
Informácie o vydavateľovi: American Nuclear Society (ANS), 2019.
Rok vydania: 2019
Predmety: probabilistic risk assessment, 13. Climate action, 7. Clean energy, nuclear safety, digital I&C
Popis: 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 dokumentu: Conference object
Jazyk: English
Prístupová URL adresa: https://cris.vtt.fi/en/publications/5602077f-2420-4a4b-800c-56cbdf174e68
Prístupové číslo: edsair.dedup.wf.002..b91137b57c931c7652e09cf020db3b04
Databáza: OpenAIRE
Popis
Abstrakt: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.