The outcome of a probabilistic safety assessment (PSA) for a nuclear power plant is a combination of qualitative and quantitative results. Quantitative results of a level 1 PSA are typically presented as the Core Damage Frequency (CDF) and of a level 2 PSA as the frequency of an unacceptable radioactive release, sometimes expressed in terms of a of large (early) release (LERF/LRF). In order to judge the acceptability of PSA results, criteria for the interpretation of results and the assessment of their acceptability need to be defined. Based on work performed in the recently finalised Nordic research programme “The Validity of Safety Goals” performed in the period 2006-2010, an overview is given on the issue of probabilistic safety criteria and of ways in which the use of such criteria can contribute to increase the usefulness of PSA.
|Number of pages||13|
|Publication status||Published - 2011|
|MoE publication type||Not Eligible|
|Event||Probabilistische Sicherheitsanalysen in der Kerntechnik Symposium ‘11: PSA in der SÜ – und in Zukunft? - Heidelberg, Germany|
Duration: 26 May 2011 → 27 May 2011
|Conference||Probabilistische Sicherheitsanalysen in der Kerntechnik Symposium ‘11|
|Period||26/05/11 → 27/05/11|
- Probabilistic safety Criteri
- Risk criteria
- Safety goals
Knochenhauer, M., & Holmberg, J-E. (2011). Probabilistic safety criteria: a tool for improving the usefulness of PSA. Paper presented at Probabilistische Sicherheitsanalysen in der Kerntechnik Symposium ‘11, Heidelberg, Germany.