The effect of uncertainties in nuclear reactor plant-specific failure data on core damage frequency

Technical Report · Mon May 01 00:00:00 EDT 1995

DOI:https://doi.org/10.2172/93658· OSTI ID:93658

Martz, H F

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.

• Research Organization: Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 93658
• Report Number(s): LA-UR-95-1718; ON: DE95015324; CNN: Contract FIN L1836-5, Task 2.2; TRN: 95:018543
• Resource Relation: Other Information: PBD: May 1995
• Country of Publication: United States
• Language: English

Related Subjects

22 NUCLEAR REACTOR TECHNOLOGY
99 MATHEMATICS
COMPUTERS
INFORMATION SCIENCE
MANAGEMENT
LAW
MISCELLANEOUS
NUCLEAR POWER PLANTS
REACTOR CORES
REACTOR COMPONENTS
RELIABILITY
FAILURES
ECCS
CONTAINMENT SPRAY SYSTEMS
DATA COVARIANCES
FAULT TREE ANALYSIS
RISK ASSESSMENT
REACTOR SAFETY
DISTRIBUTION FUNCTIONS