Risk Metrics and Measures for an Extended PSA
Creators
- Wielenberg, A.1
- Loeffler, H.1
- Hasnaoui, C.2
- Burgazzi, L.3
- Cazzoli, E.4
- Jan, P.5
- La Rovere, S.6
- Siklossy, T.7
- Vitazkova, J.8
- Raimond, E.8
- Advanced Safety Assessment Methodologies: extended PSA - ASAMPSA-E, Institute for Radiological Protection and Nuclear Safety - IRSN, Nuclear Safety Division, 31 avenue de la Division Leclerc, 92 260 Fontenay-aux-Roses (France)
- 1. Gesellschaft fuer Anlagen-und Reaktorsicherheit mbH - GRS (Germany)
- 2. Arexis S.A.R.L. (France)
- 3. Italian National Agency for New Technologies Energy and the Sustainable Economic Development - ENEA (Italy)
- 4. Cazzoli Consulting - CCA (Italy)
- 5. Electricite de France - EDF (France)
- 6. NIER Ingegneria (Italy)
- 7. Nuklearis Biztonsagi Kutatointezet - NUBIKI (Hungary)
- 8. Institute for Radiological Protection and Nuclear Safety - IRSN (France)
Description
This report provides a review of the main used risk measures for Level 1 and Level 2 PSA. It depicts their advantages, limitations and disadvantages and develops some more precise risk measures relevant for extended PSAs and helpful for decision-making. This report does not recommend or suggest any quantitative value for the risk measures. It does not discuss in details decision-making based on PSA results neither. The choice of one appropriate risk measure or a set of risk measures depends on the decision making approach as well as on the issue to be decided. The general approach for decision making aims at a multi-attribute approach. This can include the use of several risk measures as appropriate. Section 5 provides some recommendations on the main risk metrics to be used for an extended PSA. For Level 1 PSA, Fuel Damage Frequency and Radionuclide Mobilization Frequency are recommended. For Level 2 PSA, the characterization of loss of containment function and a total risk measure based on the aggregated activity releases of all sequences rated by their frequencies is proposed. (authors)
Files
Additional details
Identifiers
Publishing Information
- Imprint Pagination
- 140 p.
- Report number
- IRSN-PSN-RES-SAG--2017-0018
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 48055421
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- CONTAINMENT BUILDINGS; DAMAGE; DECISION MAKING; FISSION PRODUCT RELEASE; HAZARDS; NUCLEAR POWER PLANTS; PROBABILISTIC ESTIMATION; REACTOR CORES; RECOMMENDATIONS; REGRESSION ANALYSIS; RELIABILITY; RISK ASSESSMENT; SENSITIVITY ANALYSIS; SPENT FUEL STORAGE
- Descriptors DEC
- BUILDINGS; CALCULATION METHODS; CONTAINMENT; MATHEMATICS; NUCLEAR FACILITIES; POWER PLANTS; REACTOR COMPONENTS; STATISTICS; STORAGE; THERMAL POWER PLANTS
Optional Information
- Notes
- 141 refs.; Available from the INIS Liaison Officer for France, see the 'INIS contacts' section of the INIS website for current contact and E-mail addresses: http://www.iaea.org/inis/Contacts/
- Secondary number(s)
- ASAMPSA-E-WP30-D30.7--2017-31-v3