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 | United States |
| City | Charleston |
| Period | 28/04/19 → 3/05/19 |
| Internet address |
Keywords
- probabilistic risk assessment
- digital I&C
- nuclear safety
Fingerprint Dive into the research topics of 'Comparative application of digital I&C modeling approaches for PSA'. Together they form a unique fingerprint.
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.