Abstract
| 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 | United States |
| City | Charleston |
| Period | 28/04/19 → 3/05/19 |
| Internet address |
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Keywords
- probabilistic risk assessment
- digital I&C
- nuclear safety
Cite this
}
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 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
ER -