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

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 proceeding › Conference article in proceedings › Scientific › peer-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 language	English
Title of host publication	International Topical Meeting on Probabilistic Safety Assessment and Analysis (PSA 2019)
Publisher	American Nuclear Society (ANS)
Pages	321-329
Number of pages	9
ISBN (Electronic)	978-0-89448-763-7
ISBN (Print)	978-0-89448-764-4
Publication status	Published - 3 May 2019
MoE publication type	A4 Article in a conference publication
Event	16th 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 2019 → 3 May 2019 http://psa.ans.org/2019/

Conference

Conference	16th ANS International Conference on Probabilistic Safety Assessment & Analysis, PSA 2019
Abbreviated title	PSA 2019
Country/Territory	United States
City	Charleston
Period	28/04/19 → 3/05/19
Internet address	http://psa.ans.org/2019/

Keywords

probabilistic risk assessment
digital I&C
nuclear safety

Cite this

Porthin, M., Shin, S. M., 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) (pp. 321-329). American Nuclear Society (ANS).

@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 = may,

day = "3",

language = "English",

isbn = "978-0-89448-764-4",

pages = "321--329",

booktitle = "International Topical Meeting on Probabilistic Safety Assessment and Analysis (PSA 2019)",

publisher = "American Nuclear Society (ANS)",

address = "United States",

note = "16th ANS International Conference on Probabilistic Safety Assessment \& Analysis, PSA 2019 : International Topical Meeting on Probabilistic Safety Assessment and Analysis, PSA 2019 ; Conference date: 28-04-2019 Through 03-05-2019",

url = "http://psa.ans.org/2019/",

}

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, South Carolina, United States, 28/04/19.

Comparative application of digital I&C modeling approaches for PSA. / Porthin, Markus; Shin, Sung Min; Tyrväinen, Tero et al.
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 proceeding › Conference article in proceedings › Scientific › peer-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.

KW - probabilistic risk assessment

KW - digital I&C

KW - nuclear safety

M3 - Conference article in proceedings

SN - 978-0-89448-764-4

SP - 321

EP - 329

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

PB - American Nuclear Society (ANS)

T2 - 16th ANS International Conference on Probabilistic Safety Assessment & Analysis, PSA 2019

Y2 - 28 April 2019 through 3 May 2019

ER -

Comparative application of digital I&C modeling approaches for PSA

Abstract

Conference

Keywords

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