Operator reliability study for Probabilistic Safety Analysis of an operating research reactor

Faizal K.P. Kunchi Mohamed, A. Hassan, R. Yahaya, Irman Abdul Rahman, M. Maskin, P. Praktom, F. Charlie

Research output: Contribution to journalArticle

4 Citations (Scopus)

Abstract

A Level 1 Probabilistic Safety Analysis (PSA) for the TRIGA Mark II research reactor of Malaysian Nuclear Agency has been developed to evaluate the potential risk in its operation. In conjunction to this PSA development, Human Reliability Analysis (HRA) is performed in order to determine human contribution to the risk. The aim of this study is to qualitatively analyze human actions (HAs) involved in the operation of this reactor according to the qualitative part of the HRA framework for PSA which is namely the identification, qualitative screening and modeling of HAs. By performing this framework, Human Failure Events (HFEs) of significant impact to the reactor safety are systematically analyzed and incorporated into the PSA structure. A part of the findings in this study will become the input for the subsequent quantitative part of the HRA framework, i.e. the Human Error Probability (HEP) quantification.

Original languageEnglish
Pages (from-to)409-415
Number of pages7
JournalAnnals of Nuclear Energy
Volume80
DOIs
Publication statusPublished - 2015

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Research reactors
Reliability analysis
Screening

Keywords

  • Human action
  • Human Failure Event
  • Human Reliability Analysis
  • Probabilistic Safety Analysis
  • Qualitative screening
  • Research reactor

ASJC Scopus subject areas

  • Nuclear Energy and Engineering

Cite this

Operator reliability study for Probabilistic Safety Analysis of an operating research reactor. / K.P. Kunchi Mohamed, Faizal; Hassan, A.; Yahaya, R.; Abdul Rahman, Irman; Maskin, M.; Praktom, P.; Charlie, F.

In: Annals of Nuclear Energy, Vol. 80, 2015, p. 409-415.

Research output: Contribution to journalArticle

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