Comparative application of digital I&C modeling approaches for PSA

Markus Porthin, Sung Min Shin, Tero Tyrväinen, Christian Mueller, Ewgenij Piljugin, Jan Stiller, Richard Quatrain, Leo Granseigne, Hans Brinkman, Paolo Picca, Joshua Gordon, Jiri Sedlak

    Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

    Abstract

    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.
    Original languageEnglish
    Title of host publicationInternational Topical Meeting on Probabilistic Safety Assessment and Analysis (PSA 2019)
    PublisherAmerican Nuclear Society ANS
    Pages321-329
    Number of pages9
    ISBN (Electronic)978-0-89448-763-7
    ISBN (Print)978-0-89448-764-4
    Publication statusPublished - 3 May 2019
    MoE publication typeA4 Article in a conference publication
    Event16th ANS International Conference on Probabilistic Safety Assessment & Analysis, PSA 2019: International Topical Meeting on Probabilistic Safety Assessment and Analysis - Marriott Charleston, Charleston, United States
    Duration: 28 Apr 20193 May 2019
    http://psa.ans.org/2019/

    Conference

    Conference16th ANS International Conference on Probabilistic Safety Assessment & Analysis, PSA 2019
    Abbreviated titlePSA 2019
    CountryUnited States
    CityCharleston
    Period28/04/193/05/19
    Internet address

    Fingerprint

    Software reliability
    Boiling water reactors
    Nuclear energy
    Risk assessment
    Nuclear power plants
    Telecommunication networks

    Keywords

    • probabilistic risk assessment
    • digital I&C
    • nuclear safety

    Cite this

    Porthin, M., Shin, S. M., Tyrväinen, T., Mueller, C., Piljugin, E., Stiller, J., ... Sedlak, J. (2019). Comparative application of digital I&C modeling approaches for PSA. In International Topical Meeting on Probabilistic Safety Assessment and Analysis (PSA 2019) (pp. 321-329). American Nuclear Society ANS.
    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. / Comparative application of digital I&C modeling approaches for PSA. International Topical Meeting on Probabilistic Safety Assessment and Analysis (PSA 2019). American Nuclear Society ANS, 2019. pp. 321-329
    @inproceedings{5602077f24204a4b800c56cbdf174e68,
    title = "Comparative application of digital I&C modeling approaches for PSA",
    abstract = "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.",
    keywords = "probabilistic risk assessment, digital I&C, nuclear safety",
    author = "Markus Porthin and Shin, {Sung Min} and Tero Tyrv{\"a}inen and Christian Mueller and Ewgenij Piljugin and Jan Stiller and Richard Quatrain and Leo Granseigne and Hans Brinkman and Paolo Picca and Joshua Gordon and Jiri Sedlak",
    year = "2019",
    month = "5",
    day = "3",
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    Porthin, M, Shin, SM, Tyrväinen, T, Mueller, C, Piljugin, E, Stiller, J, Quatrain, R, Granseigne, L, Brinkman, H, Picca, P, Gordon, J & Sedlak, J 2019, Comparative application of digital I&C modeling approaches for PSA. in International Topical Meeting on Probabilistic Safety Assessment and Analysis (PSA 2019). American Nuclear Society ANS, pp. 321-329, 16th ANS International Conference on Probabilistic Safety Assessment & Analysis, PSA 2019, Charleston, United States, 28/04/19.

    Comparative application of digital I&C modeling approaches for PSA. / 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.

    International Topical Meeting on Probabilistic Safety Assessment and Analysis (PSA 2019). American Nuclear Society ANS, 2019. p. 321-329.

    Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

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    AU - Porthin, Markus

    AU - Shin, Sung Min

    AU - Tyrväinen, Tero

    AU - Mueller, Christian

    AU - Piljugin, Ewgenij

    AU - Stiller, Jan

    AU - Quatrain, Richard

    AU - Granseigne, Leo

    AU - Brinkman, Hans

    AU - Picca, Paolo

    AU - Gordon, Joshua

    AU - Sedlak, Jiri

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    N2 - 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.

    AB - 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.

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    PB - American Nuclear Society ANS

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    Porthin M, Shin SM, Tyrväinen T, Mueller C, Piljugin E, Stiller J et al. Comparative application of digital I&C modeling approaches for PSA. In International Topical Meeting on Probabilistic Safety Assessment and Analysis (PSA 2019). American Nuclear Society ANS. 2019. p. 321-329