Estimation of human-error probabilities from expert judgment for use in probabilistic risk assessment of nuclear power plants. [PWR; BWR]
Conference
·
OSTI ID:5911953
A human reliability research program, sponsored by the Nuclear Regulatory Commission (NRC), is being performed by Sandia National Laboratories (SNL) and SNL contractors. Primary objectives of the program are to develop human performance models, human reliability analysis (HRA) methods, and estimates of human error probabilities (HEPs) for nuclear power plant (NPP) tasks. This information is needed to perform HRAs in probabilistic risk assessments (PRAs) of NPPs. The human reliability research program is being funded by the Office of Nuclear Regulatory Research and managed by the Division of Facility Operations.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (USA)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 5911953
- Report Number(s):
- SAND-83-1701C; CONF-8310143-1; ON: DE83016751
- Country of Publication:
- United States
- Language:
- English
Similar Records
Modeling and Quantification of Team Performance in Human Reliability Analysis for Probabilistic Risk Assessment
Multidisciplinary framework for human reliability analysis with an application to errors of commission and dependencies
Generating human reliability estimates using expert judgment. Volume 2. Appendices. [PWR; BWR]
Conference
·
Sun Jun 01 00:00:00 EDT 2014
·
OSTI ID:1149011
Multidisciplinary framework for human reliability analysis with an application to errors of commission and dependencies
Technical Report
·
Tue Aug 01 00:00:00 EDT 1995
·
OSTI ID:106594
Generating human reliability estimates using expert judgment. Volume 2. Appendices. [PWR; BWR]
Technical Report
·
Wed Oct 31 23:00:00 EST 1984
·
OSTI ID:6180923
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
BWR TYPE REACTORS
ENGINEERING
HUMAN FACTORS
HUMAN FACTORS ENGINEERING
NORTH AMERICA
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
OPERATION
PERSONNEL
POWER PLANTS
PWR TYPE REACTORS
REACTOR OPERATION
REACTOR OPERATORS
REACTOR SAFETY
REACTORS
RISK ASSESSMENT
SAFETY
THERMAL POWER PLANTS
USA
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
BWR TYPE REACTORS
ENGINEERING
HUMAN FACTORS
HUMAN FACTORS ENGINEERING
NORTH AMERICA
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
OPERATION
PERSONNEL
POWER PLANTS
PWR TYPE REACTORS
REACTOR OPERATION
REACTOR OPERATORS
REACTOR SAFETY
REACTORS
RISK ASSESSMENT
SAFETY
THERMAL POWER PLANTS
USA
WATER COOLED REACTORS
WATER MODERATED REACTORS