| Investigation on the effect of 238U replacement with 232Th in small modular reactor (SMR) fuel matrix EH Uguru, SFA Sani, MU Khandaker, MH Rabir Progress in Nuclear Energy 118, 103108, 2020 | 35 | 2020 |
| Neutron flux and power in RTP core-15 MH Rabir, MRM Zin, MD Usang, AMJ Bayar, NSB Hamzah AIP Conference Proceedings 1704 (1), 2016 | 23 | 2016 |
| Review of the microheterogeneous thoria‐urania fuel for micro‐sized high temperature reactors MH Rabir, AF Ismail, MS Yahya International Journal of Energy Research 45 (8), 11440-11458, 2021 | 20 | 2021 |
| A comparative study on the impact of Gd2O3 burnable neutron absorber in UO2 and (U, Th) O2 fuels EH Uguru, SFA Sani, MU Khandaker, MH Rabir, JA Karim Nuclear Engineering and Technology 52 (6), 1099-1109, 2020 | 17 | 2020 |
| Radiation shielding properties of ferro-boron concrete MS Sarkawi, MRM Zain, MH Rabir, FM Idris, J Zainal IOP Conference Series: Materials Science and Engineering 298 (1), 012037, 2018 | 15 | 2018 |
| Modeling the PUSPATI TRIGA Reactor using MCNP code MH Rabir, MD Usang, NS Hamzah, JA Karim, MA Sharifuldin Salleh | 12 | 2012 |
| Neutronics calculation of the conceptual TRISO duplex fuel rod design MH Rabir, AF Ismail, MS Yahya Nuclear Materials and Energy 27, 101005, 2021 | 11 | 2021 |
| Determination of neutronic parameters of RTP core using MCNP code HR Mohamad, MD Usang, SH Naim, AK Julia, ASS Mohd Jurnal Sains Nuklear Malaysia 25 (1), 46-60, 2013 | 11 | 2013 |
| Burn‐up calculation of the neutronic and safety parameters of thorium‐uranium mixed oxide fuel cycle in a Westinghouse small modular reactor EH Uguru, SF Abdul Sani, MU Khandaker, MH Rabir, JA Karim, DU Onah, ... International journal of energy research 45 (8), 12013-12028, 2021 | 10 | 2021 |
| Neutronics calculation of RTP core MHB Rabir, MRBM Zin, JBA Karim, AMBJ Bayar, MDA Usang, ... AIP Conference Proceedings 1799 (1), 2017 | 9 | 2017 |
| Collimator and shielding design for boron neutron capture therapy (BNCT) facility at TRIGA MARK II reactor MRM Solleh, AABIN MOHAMED Journal of Nuclear and Related Technologies 8 (02), 41-48, 2011 | 9 | 2011 |
| Measurement and simulation of thermal neutron flux distribution in the RTP core MHB Rabir, B Abi Muttaqin, BH Na’im Syauqi, MKAB Mustafa, JBA Karim, ... IOP Conference Series: Materials Science and Engineering 298 (1), 012029, 2018 | 8 | 2018 |
| Measurement of the power and temperature reactivity coefficients of the RTP TRIGA reactor MH Rabir Nuclear Engineering and Design 265, 269-271, 2013 | 8 | 2013 |
| Actinide and non-actinide production from UO2 fuel in W-SMR: effects of gadolinium burnable absorber EH Uguru, SFA Sani, MU Khandaker, MH Rabir Annals of Nuclear Energy 137, 107083, 2020 | 7 | 2020 |
| Neutron flux characterisation of irradiation facilities in RTP MH Rabir, JA Karim, MRM Zin Jurnal Sains Nuklear Malaysia 29 (2), 33-43, 2017 | 7 | 2017 |
| In-core neutron flux determination MH Rabir, JA Karim, NM Said, MKA Mustafa, AMJ Bayar, MHA Khalil, ... Nuclear Bulletin of Malaysia 18, 26-28, 2016 | 6 | 2016 |
| The neutronics effect of TRISO duplex fuel packing fractions and their comparison with homogeneous thorium‐uranium fuel MH Rabir, AF Ismail, MS Yahya International Journal of Energy Research 46 (13), 19072-19089, 2022 | 5 | 2022 |
| A micro-sized high-temperature thorium reactor with Duplex TRISO fuel with enhanced thorium utilization compared to the SBU configuration MH Rabir, AF Ismail, MS Yahya Fuel 354, 129316, 2023 | 4 | 2023 |
| Effect of kGy neutron doses on polymer composite consists of poly (vinylidene difluoride)–lithium bis (oxalato) borate NA Heffny, MU Khandaker, Z Osman, HJ Woo, MH Rabir, AK Arof Radiation Physics and Chemistry 189, 109747, 2021 | 4 | 2021 |
| Impact of weight percent gadolinium and the number of its fuel rods on the neutronic and safety parameters EH Uguru, MFBA Sapli, SFA Sani, MU Khandaker, MH Rabir, JA Karim, ... Radiation Physics and Chemistry 188, 109686, 2021 | 4 | 2021 |
Mark Dennis UsangMalaysian Nuclear AgencyVerified email at nm.gov.my
