《《Thermal hydraulic analysis of Syrian MNSR research reactor using》.pdf

Annals of Nuclear Energy 37 (2010) 572–581 Contents lists available at ScienceDirect Annals of Nuclear Energy journal homepage: www.elsevier .com/locate/anucene Thermal hydraulic analysis of Syrian MNSR research reactor using RELAP5/Mod3.2 code H. Omar *, N. Ghazi, F. Alhabit, A. Hainoun Nuclear Engineering Department, Atomic Energy Commission, P.O. Box 6091, Damascus, Syria a r t i c l e i n f o a b s t r a c t Article history: This paper presents the development and validation of a MNSR-RELAP5 model. MNSR is a 30 kW, light- Received 7 September 2009 water moderated and cooled, beryllium-reflected, tank in pool type research reactor. A RELAP5 model Received in revised form 10 December 2009 was set up to simulate the entire MNSR system. The model represents all reactor components of primary Accepted 27 December 2009 and secondary loops with the corresponding neutronic and thermal hydraulic characteristics. Under the Available online 29 January 2010 MNSR operation conditions of natural circulation, normal operation, step reactivity transients and reac- tivity insertion accidents are simulated. The RELAP5 model was validated by comparing measured and calculated data for the Syrian MNSR reactor. Comparisons include parameters of normal operation at constant power, step reactivity transient