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
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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.",
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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",
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month = "5",
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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

TY - GEN

T1 - Comparative application of digital I&C modeling approaches for PSA

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

PY - 2019/5/3

Y1 - 2019/5/3

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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SN - 978-0-89448-764-4

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

PB - American Nuclear Society ANS

ER -

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