Published April 2009
| Version v1
Journal article
Development and application for quantification of cognitive reliability and error analysis method
Creators
- 1. Department of Safety and Environment Engineering, Hunan Inst. of Technology, Hengyang (China)
- 2. Institute of Nuclear and New Energy Technology, Tsinghua Univ., Beijing (China)
- 3. China Nuclear Power Technology Research Institute, Beijing (China)
Description
Cognitive reliability and error analysis method (CREAM) is a representative method of the so-called second generation human reliability analysis (HRA) method and can be used in both retrospective and prospective analysis. Not only the general CREAM was descried,but also using the context effect factor β and common performance condition (CPC) factor, the formula was obtained for calculation of cognitive error probability in probability safety assessment (PSA)/HRA of nuclear power plant and to provide a simplified CREAM quantification process. One example was provided in the steam generator tube rupture (SGTR) event of Qinshan I Nuclear Power Plant. The results give a more validated information for future application of PSA/HRA. (authors)
Additional details
Publishing Information
- Journal Title
- Atomic Energy Science and Technology
- Journal Volume
- 43
- Journal Issue
- 4
- Journal Page Range
- p. 322-327
- ISSN
- 1000-6931
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 42073247
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ERRORS; HUMAN FACTORS; INFORMATION; NUCLEAR POWER PLANTS; PERFORMANCE; PROBABILITY; QINSHAN-1 REACTOR; RELIABILITY; RISK ASSESSMENT; RUPTURES; STEAM GENERATORS; TUBES
- Descriptors DEC
- BOILERS; ENRICHED URANIUM REACTORS; FAILURES; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 2 figs., 4 tabs., 7 refs.