Published October 2009
| Version v1
Miscellaneous
Cutset Quantification Error Evaluation for Shin-Kori 1 and 2 PSA model
Description
Probabilistic safety assessments (PSA) for nuclear power plants (NPPs) are based on the minimal cut set (MCS) quantification method. In PSAs, the risk and importance measures are computed from a cutset equation mainly by using approximations. The conservatism of the approximations is also a source of quantification uncertainty. In this paper, exact MCS quantification methods which are based on the 'sum of disjoint products (SDP)' logic and Inclusion-exclusion formula are applied and the conservatism of the MCS quantification results in Shin-Kori 1 and 2 PSA is evaluated
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS autumn meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [2 p.]
Conference
- Title
- 2009 autumn meeting of the KNS
- Dates
- 29-30 Oct 2009
- Place
- Kyungju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 41027340
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ERRORS; EVALUATION; HAZARDS; NUCLEAR POWER PLANTS; PROBABILITY; PWR TYPE REACTORS; SAFETY ANALYSIS
- Descriptors DEC
- ENRICHED URANIUM REACTORS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 3 refs, 1 fig, 2 tabs