Heat transfer performance evaluation for turbulent flow through a tube with twisted wire brush inserts by Bhuiya, M.M.K., Chowdhury, M.S.U., Islam, M., Ahamed, J.U., Khan, M.J.H., Sarker, M.R.I., Saha, M.

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Validation study of the reactor physics lattice transport code WIMSD-5B by TRX and BAPL critical experiments of light water reactors by Khan, MJH, Alam, ABMK, Ahsan, M H, Mamun, KAA, Islam, SMA

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Thermal hydraulic transient study of 3<ce:hsp sp="0.25"/>MW TRIGA Mark-II research reactor of Bangladesh using the EUREKA-2/RR code by Badrun, N H, Altaf, M H, Khan, MJH, Mahmood, MS, Motalab, MA, Lyric, ZI

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Advanced Control Technique for Substrate Feed Rate Regulation of a Fed Batch Fermentation by Rashid, M.M., ., Hizbullah, Mohammad, Noor, Khan, M. Jakir H

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Computational analysis of neutronic parameters for TRIGA Mark-II research reactor using evaluated nuclear data libraries by Uddin, M.N., Sarker, M.M., Khan, M.J.H., Islam, S.M.A.

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Validation of CENDL and JEFF evaluated nuclear data files for TRIGA calculations through the analysis of integral parameters of TRX and BAPL benchmark lattices of thermal reactors by Uddin, M.N., Sarker, M.M., Khan, M.J.H., Islam, S.M.A.

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Criticality and Safety Parameter Studies of a 3-MW TRIGA MARK-II Research Reactor and Validation of the Generated Cross-Section Library and Computational Method by Bhuiyan, S. I., Mondal, M. A. W., Sarker, M. M., Rahman, M., Shahdatullah, M. S., Huda, M. Q., Chakrobortty, T. K., Khan, M. J. H.

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