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Title: Fundamental approaches for analysis thermal hydraulic parameter for Puspati Research Reactor

The 1-MW PUSPATI Research Reactor (RTP) is the one and only nuclear pool type research reactor developed by General Atomic (GA) in Malaysia. It was installed at Malaysian Nuclear Agency and has reached the first criticality on 8 June 1982. Based on the initial core which comprised of 80 standard TRIGA fuel elements, the very fundamental thermal hydraulic model was investigated during steady state operation using the PARET-code. The main objective of this paper is to determine the variation of temperature profiles and Departure of Nucleate Boiling Ratio (DNBR) of RTP at full power operation. The second objective is to confirm that the values obtained from PARET-code are in agreement with Safety Analysis Report (SAR) for RTP. The code was employed for the hot and average channels in the core in order to calculate of fuel’s center and surface, cladding, coolant temperatures as well as DNBR’s values. In this study, it was found that the results obtained from the PARET-code showed that the thermal hydraulic parameters related to safety for initial core which was cooled by natural convection was in agreement with the designed values and safety limit in SAR.
Authors:
; ; ;  [1] ;  [2]
  1. Reactor Technology Centre, Technical Support Division, Malaysia Nuclear Agency, Ministry of Science, Technology and Innovation, Bangi, 43000, Kajang, Selangor Darul Ehsan (Malaysia)
  2. Universiti Teknologi Malaysia, 80350, Johor Bahru, Johor Darul Takzim (Malaysia)
Publication Date:
OSTI Identifier:
22494519
Resource Type:
Journal Article
Resource Relation:
Journal Name: AIP Conference Proceedings; Journal Volume: 1704; Journal Issue: 1; Conference: iNuSTEC2015: International muclear science, technology and engineering conference 2015, Negeri Sembilan (Malaysia), 17-19 Aug 2015; Other Information: (c) 2016 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; CLADDING; FUEL ELEMENTS; NATURAL CONVECTION; NUCLEATE BOILING; PUSPATI; RESEARCH REACTORS; SAFETY ANALYSIS; THERMAL HYDRAULICS; TRIGA TYPE REACTORS