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Title: Development and methodology of level 1 probability safety assessment at PUSPATI TRIGA Reactor

As a consequence of the accident at the Fukushima Dai-ichi Nuclear Power Plant in Japan, the safety aspects of the one and only research reactor (31 years old) in Malaysia need be reviewed. Based on this decision, Malaysian Nuclear Agency in collaboration with Atomic Energy Licensing Board and Universiti Kebangsaan Malaysia develop a Level-1 Probability Safety Assessment on this research reactor. This work is aimed to evaluate the potential risks of incidents in RTP and at the same time to identify internal and external hazard that may cause any extreme initiating events. This report documents the methodology in developing a Level 1 PSA performed for the RTP as a complementary approach to deterministic safety analysis both in neutronics and thermal hydraulics. This Level-1 PSA work has been performed according to the procedures suggested in relevant IAEA publications and at the same time numbers of procedures has been developed as part of an Integrated Management System programme implemented in Nuclear Malaysia.
Authors:
; ; ; ; ;  [1] ;  [2] ;  [3]
  1. Malaysian Nuclear Agency, MOSTI, Bangi, 43000 Kajang, Selangor (Malaysia)
  2. Atomic Energy Licensing Board, MOSTI, 43800 Dengkil, Selangor (Malaysia)
  3. Universiti Kebangsaan Malaysia, Bangi, Selangor (Malaysia)
Publication Date:
OSTI Identifier:
22266080
Resource Type:
Journal Article
Resource Relation:
Journal Name: AIP Conference Proceedings; Journal Volume: 1584; Journal Issue: 1; Conference: iNuSTEC2013: International nuclear science, technology and engineering conference 2013, Kuala Lumpur (Malaysia), 30 Sep - 2 Oct 2013; Other Information: (c) 2014 AIP Publishing LLC; Country of input: International Atomic Energy Agency (IAEA)
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; ACCIDENTS; HAZARDS; NUCLEAR ENERGY; NUCLEAR POWER PLANTS; PROBABILITY; RESEARCH REACTORS; RISK ASSESSMENT; RTP REACTOR; SAFETY ANALYSIS; THERMAL HYDRAULICS