| Preliminary core calculation on reactivity compensation for SiC matrix fuel compact HTTR with Erbium burnable poison and Plutonium fissile material Y Nishimura, MA Allaf, S Okita, M Goto, K Okamoto International Conference on Nuclear Engineering 86502, V015T16A055, 2022 | 4 | 2022 |
| The development of TM2-RIA code for TRIGA type research reactors MA Allaf, SŞ Lüle, Ü Çolak Annals of Nuclear Energy 145, 107545, 2020 | 4 | 2020 |
| Core performance study of HTGR-SiC for higher burn up: thorium based fuel loading pattern Y Nishimura, S Okita, M Goto, M Allaf, K Okamoto M&C 2023-The International Conference on Mathematics and Computational …, 2023 | 3 | 2023 |
| Conceptualization of the Micro Research Reactor Cooled by Heat Pipes (MRR-HP), Part-I: neutronics analyses M Allaf, K Okamoto, N Erkan Journal of Nuclear Science and Technology 60 (3), 299-319, 2023 | 2 | 2023 |
| Conceptualization of the micro research reactor cooled by heat pipes (MRR-HP), part-II: safety analyses M Allaf, K Okamoto, S Suzuki, N Erkan Journal of Nuclear Science and Technology 60 (8), 881-899, 2023 | 2 | 2023 |
| Uncertainty quantification of unconfined spill fire data by coupling Monte Carlo and artificial neural networks E Sahin, B Lattimer, MA Allaf, J Pacheco Duarte Journal of Nuclear Science and Technology, 1-14, 2024 | 1 | 2024 |
| The Investigation of the Sensitivity of Monte Carlo Simulation Results to Modelling Approaches for Nuclear Reactor Cores M Allaf, SŞ Lüle, Ü Çolak Avrupa Bilim ve Teknoloji Dergisi, 110-115, 2022 | 1 | 2022 |
| Doppler Broadening Effect on Reactivity Feedback in ITU TRIGA MARK II Research Reactor M Allaf, F Kutbay, SS Lule, U Colak International Conference Nuclear Energy for New Europe, 2018 | 1 | 2018 |
| Safety Analysis of Chromium-Coated Accident-Tolerant Fuels with Increased Enrichment and Extended Burnup [Slides] MA Allaf, A Whitmeyer, JP Duarte, B Lindley Idaho National Laboratory (INL), Idaho Falls, ID (United States), 2024 | | 2024 |
| Analysis Of Reactivity İnitiated Accidents For ITU Triga Mark Ii Research Reactor And The Development Of A New Analysis Code M Allaf Energy Institute, 2019 | | 2019 |
| Oxidation model of the Accident Tolerant Fuel implemented in NuScale Reactor using MELCOR Code MA Allaf, G Ejnik, WH Jung, M Corradini, K Shirvan, JP Duarte | | |
| Numerical Investigation of a Single Droplet Impact onto Hot Surface by VOF Method at High Weber Numbers M Allaf, A Gultekin, U Colak | | |
