Probabilistic safety criteria: a tool for improving the usefulness of PSA

M. Knochenhauer, Jan-Erik Holmberg

Research output: Contribution to conferenceConference articleScientific

Abstract

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.
Original languageEnglish
Number of pages13
Publication statusPublished - 2011
MoE publication typeNot Eligible
EventProbabilistische Sicherheitsanalysen in der Kerntechnik Symposium ‘11: PSA in der SÜ – und in Zukunft? - Heidelberg, Germany
Duration: 26 May 201127 May 2011

Conference

ConferenceProbabilistische Sicherheitsanalysen in der Kerntechnik Symposium ‘11
CountryGermany
CityHeidelberg
Period26/05/1127/05/11

Fingerprint

Nuclear power plants

Keywords

  • PSA
  • Probabilistic safety Criteri
  • Risk criteria
  • Safety goals

Cite this

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.
Knochenhauer, M. ; Holmberg, Jan-Erik. / Probabilistic safety criteria : a tool for improving the usefulness of PSA. Paper presented at Probabilistische Sicherheitsanalysen in der Kerntechnik Symposium ‘11, Heidelberg, Germany.13 p.
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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, 26/05/11 - 27/05/11, .

Probabilistic safety criteria : a tool for improving the usefulness of PSA. / Knochenhauer, M.; Holmberg, Jan-Erik.

2011. Paper presented at Probabilistische Sicherheitsanalysen in der Kerntechnik Symposium ‘11, Heidelberg, Germany.

Research output: Contribution to conferenceConference articleScientific

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AU - Knochenhauer, M.

AU - Holmberg, Jan-Erik

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N2 - 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.

AB - 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.

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Knochenhauer M, Holmberg J-E. Probabilistic safety criteria: a tool for improving the usefulness of PSA. 2011. Paper presented at Probabilistische Sicherheitsanalysen in der Kerntechnik Symposium ‘11, Heidelberg, Germany.