[1] Hossain, S.M., Zulquarnain, M.A., Kamal, I. and Islam, M.N. (2011) Current Status and Perspectives of Nuclear Reactor Based Research in Bangladesh. IAEA, Vienna, 7-14.
[2] Huda, M.Q., Bhuiyan, S.I., Chakroborty, T.K., Sarker, M.M. and Mondal, M.A.W. (2001) Thermal Hydraulic Analysis of the 3 MW TRIGA MARK-II Research Reactor. Nuclear Technology, 135, 51-66.
[3] FSAR (2006) Final Safety Analysis Report for 3 MW TRIGA MARK-II Research Reactor at AERE, Savar, Dhaka, Bangladesh. BAEC, Dhaka.
[4] Rahman, M.M., Hussain, M.S., Imtiaz, M.A. and Huda, M.Q. (2012) Computational Analysis of Thermo-Hydraulic Behaviour of TRIGA Research Reactor. Annals of Nuclear Energy, 49, 48-56.
http://dx.doi.org/10.1016/j.anucene.2012.05.034
[5] Kaminaga, M. (1994) COOLOD-N2: A Computer Code, for the Analyses of Steady-State Thermal Hydraulics in Research Reactors, JAERI Report. Japan Atomic Energy Research Institute, Tokai-mura, Ibaraki.
[6] Sudo, Y., Ikawa, H. and Kaminaga, M. (1985) Development of Heat Transfer Package for Core Thermal Hydraulics Design and Analysis of Upgradded JRR-3. Proceedings of the International Meeting of Reduced Enrichment for Research and Test Reactors, Petten, 14-16 October 1985, 363-372.
[7] General Atomics (1979) 10 MW TRIGA-LEU Fuel and Reactor Design Description. General Atomics, San Diego.
[8] Obenchain, C.F. (1969) PARET—A Program for the Analysis of Reactor Transients. IDO-17282, Idaho Atomic Energy Division, USAEC, Idaho.
[9] 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