| Power peaking factor prediction using ANFIS method NSM Ali, K Hamzah, F Idris, NA Basri, MS Sarkawi, MA Sazali, H Rabir, ... Nuclear Engineering and Technology 54 (2), 608-616, 2022 | 12 | 2022 |
| Neutron and gamma ray fluences measurement at radial Beam Port 1 of TRIGA MARK II PUSPATI research reactor MAA Rosdi, PS Goh, F Idris, S Shalbi, MS Sarkawi, NSM Ali, NL Jamsari, ... IOP Conference Series: Materials Science and Engineering 298 (1), 012033, 2018 | 7 | 2018 |
| Analysis of boron epoxy resin composite in morphology, neutron radiography, and thermal neutron shielding performance NAM Yunus, MA Sazali, K Yazid, WNW Salleh, MZ Abdullah, FM Idris, ... Radiation Physics and Chemistry 204, 110670, 2023 | 6 | 2023 |
| Polyethylene composite with boron and tungsten additives for mixed radiation shielding MA Sazali, NKAM Rashid, K Hamzah, FM Idris, MS Sarkawi, NSM Ali IOP Conference Series: Materials Science and Engineering 1231 (1), 012010, 2022 | 6 | 2022 |
| Thermal neutron flux measurement using self-powered neutron detector (SPND) at out-core locations of TRIGA PUSPATI Reactor (RTP) NSM Ali, K Hamzah, FM Idris, MH Rabir IOP Conference Series: Materials Science and Engineering 298 (1), 012027, 2018 | 5 | 2018 |
| Multiprocessing implementation for MCNP using Python MA Sazali, MS Sarkawi, NSM Ali IOP Conference Series: Materials Science and Engineering 1231 (1), 012003, 2022 | 3 | 2022 |
| A control rod worth prediction using Adaptive Neuro-Fuzzy Inference System for Pre-Calibration Method at TRIGA PUSPATI Reactor TZ Hui, NSM Ali, MS Minhat, J Zainal, MA Sazali, MS Sarkawi, ... Annals of Nuclear Energy 200, 110410, 2024 | 2 | 2024 |
| Analysis of graphite-paraffin composite in neutron radiography, impact resistance, and thermal neutron attenuation AHM Fahmi, MA Sazali, K Yazid, AAA Bakar, NSM Ali, K Jamaluddin, ... Radiation Physics and Chemistry 218, 111639, 2024 | 2 | 2024 |
| Estimation of fuel temperature reactivity coefficient of a research reactor using ANFIS NSM Ali, K Hamzah, FM Idris, NKAM Rashid, MS Minhat, MH Rabir IOP Conference Series: Materials Science and Engineering 555 (1), 012002, 2019 | 2 | 2019 |
| Simulation of beam collimator for neutron radiography using Monte Carlo method NSM Ali, K Hamzah, R Jamro Journal of Nuclear and Related Technologies 13 (02), 1-6, 2016 | 1 | 2016 |
| Gamma radiation shielding simulation for thermoplastic elastomer and silicon rubber/alloy dopant with functional nanoparticle CC Ful, MA Sazali, K Jamaluddin, NSM Ali, MS Sarkawi IOP Conference Series: Materials Science and Engineering 1285 (1), 012010, 2023 | | 2023 |
| TERRESTRIAL GAMMA DOSE RATE MAPPING OF UNIVERSITI TEKNOLOGI MALAYSIA KY Yun, MA Sazali, NAM Kamal, NSM Ali, K Jamaluddin, MS Sarkawi, ... The Proceedings of the International Conference on Nuclear Engineering …, 2023 | | 2023 |
| Radiotherapy Communication Skills Training using Chatbot-Based Prototype (SCIMORT) A Nor, S Nur, K Muhamad, A Rozilawati, Y Noorazrul, F Muhammad, ... Journal of Medical Imaging and Radiation Sciences 53 (4), S1, 2022 | | 2022 |
| CHARACTERIZATION OF ANFIS-SC METHOD ON POWER PEAKING FACTOR NSM Ali, K Hamzah, F Idris, MA Sazali, MS Sarkawi, NA Basri, ... JOURNAL of NUCLEAR and Related TECHNOLOGIES, 31-36, 2022 | | 2022 |
| Nuclear fuel materials and its sustainability for low carbon energy system: A review MAN Azman, NSM Ali, MS Sarkawi, MA Sazali, NA Basri IOP Conference Series: Materials Science and Engineering 1231 (1), 012016, 2022 | | 2022 |
| New exposure room shielding incorporated with ferro boron concrete for neutron radiography imaging (NURI) facility at TRIGA PUSPATI Research Reactor MS Sarkawi, J Zainal, MA Sazali, NS Ali, NA Basri, MRM Zain, F Idris, ... IOP Conference Series: Materials Science and Engineering 1231 (1), 012004, 2022 | | 2022 |
| IOP Conference Series: Materials Science and Engineering NKAM Rashid, K Hamzah, MM Sies, J Zainal, MA Sazali, MS Sarkawi, ... | | 2021 |
| DEVELOPMENT OF TRIGA MARK II RESEARCH REACTOR CORE MONITORING SYSTEM USING ADAPTIVE NEURO-FUZZY INFERENCE SYSTEM NURSM ALI Universiti Teknologi Malaysia, 2020 | | 2020 |
| Polyethylene Composite Doped with Cadmium and Tungsten Oxide for Neutron-Gamma Multilayer Shielding LS Chin, MA Sazali, AA Abu Bakar, AH Ismail, R Yahya, MS Sarkawi, ... Available at SSRN 4880423, 0 | | |
| Surface Dose Assessment on A Proposed Dry Storage Facility Designed for RTP Spent Nuclear Fuel Using MCNP SB Nurlaila, Z Jasman, SMA Nur, MD Usang, J Khairulnadzmi, ... | | |
