Open AccessInternal fire probabilistic safety assessment preliminary work at research reactor TRIGA PUSPATI
Author(s) -
Zaredah Hashim,
Devintharaaj Kumar,
Mohd Fazli Zakaria,
Mohd Huzair Hussain,
Ahmad Hassan Sallehudin Mohd Sarif,
Mazleha Maskin
Publication year - 2020
Publication title -
iop conference series. materials science and engineering
Language(s) - English
Resource type - Journals
eISSN - 1757-899X
pISSN - 1757-8981
DOI - 10.1088/1757-899x/785/1/012049
Subject(s) - triga , data collection , nuclear power , work (physics) , probabilistic logic , nuclear engineering , scope (computer science) , engineering , reliability engineering , computer science , systems engineering , research reactor , mechanical engineering , statistics , physics , programming language , mathematics , quantum mechanics , artificial intelligence , neutron , nuclear physics
An internal fire analysis Level-I probabilistic safety assessment (PSA) for TRIGA PUSPATI (RTP) nuclear research reactor was initiated. Previous study on half-scope mode Level-I PSA, focusing only on internal initiating event, were developed for both full power and shutdown operational mode. Hence, in ensuring PSA remains relevant, a subsequent study to kept PSA up to date is a compulsory. The aim of this study is to present the step-by-step work done and the insights gained in identifying and screening significant compartments that are potential to had the worst consequences as an ignition sources. This preliminary study will only focus on RTP’s basement which consist of 3 compartments: switch room, battery room and basement hall. Procedure in data collection were based on IAEA document, Specific Safety Guide No. 3: Development and Application of Level 1 Probabilistic Safety Assessment for Nuclear Power Plants (SSG-3). Microsoft Excel was used as data collection media and internal fire hazard database development. A brief qualitative analysis using failure mode and effect analysis is also presented.