Quantification of initiating event frequencies and component reliability data in level 1 probabilistic safety assessment at Puspati TRIGA research reactor
Authors:
- M. MaskinMMM. Maskin
- A. HassanAHA. Hassan
- F.C. BrayonFBF.C. Brayon
- P.T. PhongsakornPPP.T. Phongsakorn
- M.F. ZakariaMZM.F. Zakaria
- Z. RamliZRZ. Ramli
- F. MohamedFMF. Mohamed
- 1 November 2018
- journal article
- research article
- Published by Elsevier in Annals of Nuclear Energy
- Vol. 121, 22-28
Abstract
No abstract availableKeywords
This publication has 4 references indexed in Scilit:
- Operator response modeling and human error probability in TRIGA Mark II research reactor probabilistic safety assessmentAnnals of Nuclear Energy, 2017
- Selection of important initiating events for Level 1 probabilistic safety assessment study at Puspati TRIGA ReactorAnnals of Nuclear Energy, 2016
- Operator reliability study for Probabilistic Safety Analysis of an operating research reactorAnnals of Nuclear Energy, 2015
- Development and methodology of level 1 probability safety assessment at PUSPATI TRIGA ReactorAIP Conference Proceedings, 2014