Published May 1995
| Version v1
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The effect of uncertainties in nuclear reactor plant-specific failure data on core damage frequency
Description
It is sometimes the case in PRA applications that reported plant-specific failure data are, in fact, only estimates which are uncertain. Even for detailed plant-specific data, the reported exposure time or number of demands is often only an estimate of the actual exposure time or number of demands. Likewise the reported number of failure events or incidents is sometimes also uncertain because incident or malfunction reports may be ambiguous. In this report we determine the corresponding uncertainty in core damage frequency which can b attributed to such uncertainties in plant-specific data using a simple but typical nuclear power reactor example
Availability note (English)
MF available from INIS under the Report Number; Also available from OSTI as DE95015324; NTIS; US Govt. Printing Office Dep.Files
27005798.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 28 p.
- Report number
- LA-UR--95-1718
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27005798
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S99: GENERAL AND MISCELLANEOUS;
- Descriptors DEI
- CONTAINMENT SPRAY SYSTEMS; DATA COVARIANCES; DISTRIBUTION FUNCTIONS; ECCS; FAILURES; FAULT TREE ANALYSIS; NUCLEAR POWER PLANTS; REACTOR COMPONENTS; REACTOR CORES; REACTOR SAFETY; RELIABILITY; RISK ASSESSMENT
- Descriptors DEC
- CONTAINMENT; CONTAINMENT SYSTEMS; ENGINEERED SAFETY SYSTEMS; NUCLEAR FACILITIES; POWER PLANTS; REACTOR PROTECTION SYSTEMS; SAFETY; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL POWER PLANTS
Optional Information
- Contract/Grant/Project number
- Contract W-7405-ENG-36; Contract FIN L1836-5, Task 2.2
- Funding organization
- Nuclear Regulatory Commission, Washington, DC (United States).