Fundamental approaches for analysis thermal hydraulic parameter for Puspati Research Reactor

Journal Article · Fri Jan 22 04:00:00 EST 2016 · AIP Conference Proceedings

DOI:https://doi.org/10.1063/1.4940064· OSTI ID:22494519

Hashim, Zaredah; Farid, Mohamad Fairus Abdul; Kassim, Mohammad Suhaimi ^[1]; Azhar, Noraishah Syahirah ^[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)

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.

• OSTI ID: 22494519
• Journal Information: AIP Conference Proceedings, Journal Name: AIP Conference Proceedings Journal Issue: 1 Vol. 1704; ISSN APCPCS; ISSN 0094-243X
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CLADDING
FUEL ELEMENTS
NATURAL CONVECTION
NUCLEATE BOILING
PUSPATI
RESEARCH REACTORS
SAFETY ANALYSIS
THERMAL HYDRAULICS
TRIGA TYPE REACTORS