scholarly journals Applying Human-performance Models to Designing and Evaluating Nuclear Power Plants: Review Guidance and Technical Basis

2009 ◽  
Author(s):  
J.M. O'Hara
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Human Performance ◽  
Performance Models ◽  
Technical Basis

A Data Bank for Human Related Events in Nuclear Power Plants

1982 ◽  
Vol 26 (9) ◽  
pp. 794-798 ◽  
Author(s):  
A. Mohsen M. Metwally ◽  
Zeinab A. Sabri ◽  
S. Keith Adams ◽  
Abdo A. Husseiny
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Human Performance ◽  
Data Bank ◽  
Data Sources ◽  
Human Reliability Analysis ◽  
Performance Shaping Factors ◽  
Comprehensive Survey ◽  
Survey And Evaluation

The authors introduce a comprehensive survey and evaluation of presently available data sources in nuclear power plants. A newly developed classification format for human related events is proposed. The format presents all necessary information in a coded form to support human reliability analysis and the assessment of performance shaping factors. Recommendations are given for improving data sources to facilitate the evaluation of man-machine interfaces and human performance in nuclear power plants.

Allowable Flaw Size of Japanese Cast Stainless Steel Pipe Using Probabilistic Fracture Mechanics Method

2017 ◽  
Author(s):  
Shotaro Hayashi ◽  
Mayumi Ochi ◽  
Kiminobu Hojo ◽  
Takahisa Yamane ◽  
Wataru Nishi
Keyword(s):  
Stainless Steel ◽  
Fracture Mechanics ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Thermal Ageing ◽  
Probabilistic Fracture Mechanics ◽  
Stainless Steel Pipe ◽  
Technical Basis ◽  
Cast Stainless Steel

The cast austenitic stainless steel (CASS) that is used for the primary loop pipes of nuclear power plants is susceptible to thermal ageing during plant operation. The Japanese JSME rules on fitness-for-service (JSME rules on FFS)[1] for nuclear power plants specify the allowable flaw depths. However, some of these allowable flaw sizes are small compared with the smallest flaw sizes, which can be detected by nondestructive testing. ASME Section XI Code Case N-838[2] recently specified the maximum tolerable flaw depths for CASS pipes determined by probabilistic fracture mechanics (PFM). In a similar way, the allowable flaw depths of CASS pipes were calculated by PFM analysis code “PREFACE”[3] which considers uncertainty of the mechanical properties of Japanese PWR CASS materials. In order to confirm the validity of PREFACE, the allowable flaw depths calculated by PREFACE were compared with the maximum tolerable flaw depths in the technical basis of Code Case N-838. As a result, although the J calculation method and the embrittlement prediction model of CASS are different, these were qualitatively consistent. In addition, the sensitivity of ferrite content to the allowable flaw depths was investigated.

Application of the Saint Code in Modelling and Analyzing Some Human Tasks in Nuclear Power Plants

1981 ◽  
Vol 25 (1) ◽  
pp. 105-109
Author(s):  
A. Mohsen M. Metwally ◽  
Zeinab A. Sabri ◽  
S. Keith Adams ◽  
Abdo A. Husseiny
Keyword(s):  
Task Analysis ◽  
Nuclear Power ◽  
Power Plants ◽  
Human Error ◽  
Nuclear Power Plants ◽  
Human Performance ◽  
Human Engineering ◽  
Performance Shaping Factors ◽  
Power Plant Operation ◽  
Error Probabilities

Two techniques useful for the simulation and analysis of human performance in tasks involving nuclear power plant operation, maintenance and testing are evaluated. The SAINT and THERP techniques are compared with respect to their relevance to conducting task analysis, estimation of human error probabilities and accounting for performance shaping factors in nuclear power plants. The results show that the SAINT is more flexible and has promising features for human engineering studies of complex systems when compared to the static THERP technique currently used in nuclear safety analysis.

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