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Boulaich, Y., Nacir, B., El Bardouni, T., Zoubair, M., El Bakkari, B., Merroun, O., El Younoussi, C., Htel, A., Boukhal, H. and Chakir, E. (2011) Steady-State Thermal Hydraulic Analysis of the Moroccan TRIGA Mark-II Reactor. Nuclear Engineering and Design, 241, 270-273. http://dx.doi.org/10.1016/j.nucengdes.2010.10.033

has been cited by the following article:

• TITLE: Steady-State Thermal-Hydraulic Analysis of TRIGA Research Reactor

  AUTHORS: Mohammad Mizanur Rahman, Mohammad Abdur R. Akond, Mohammad Khairul Basher, Md. Quamrul Huda

  KEYWORDS: COOLOD-N2, PARET, TRIGA Mark-II, DNB, Safety

  JOURNAL NAME: World Journal of Nuclear Science and Technology, Vol.4 No.2, April 14, 2014

  ABSTRACT: The COOLOD-N2 and PARET computer codes were used for a steady-state thermal hydraulic and safety analysis of the 3 MW TRIGA Mark-II research reactor located at Atomic Energy Research Establishment (AERE), Savar, Dhaka, Bangladesh. The objective of the present study is to ensure that all important safety related thermal hydraulic parameters uphold margins far below the safety limits by steady-state calculations at full power. We, therefore, have calculated the hot channel fuel centreline temperature, fuel surface temperature, cladding surface temperature, the departure from nucleate boiling (DNB) heat flux and DNB ratio, axial fuel centreline temperature and compared. The comparison indicates that the calculated values are in satisfactory agreement between the codes. The data obtained in this investigation are largely far to compromise safety of the reactor. The results can also be used to upgrade the current core configuration of the TRIGA reactor.