| Preliminary neutronic analysis of alternative cladding materials for APR-1400 fuel assembly M Alrwashdeh, SA Alameri Nuclear Engineering and Design 384, 111486, 2021 | 25 | 2021 |
| SiC and FeCrAl as potential cladding materials for APR-1400 neutronic analysis M Alrwashdeh, SA Alameri Energies 15 (10), 3772, 2022 | 21 | 2022 |
| Preliminary study of a prismatic-core advanced high-temperature reactor fuel using homogenization double-heterogeneous method M Alrwashdeh, SA Alameri, AK Alkaabi Nuclear Science and Engineering 194 (2), 163-167, 2020 | 20 | 2020 |
| Preliminary three-dimensional neutronic analysis of IFBA coated TRISO fuel particles in prismatic-core advanced high temperature reactor SA Alameri, M Alrwashdeh Annals of Nuclear Energy 163, 108551, 2021 | 16 | 2021 |
| Chromium-coated zirconium cladding neutronics impact for APR-1400 reactor core M Alrwashdeh, SA Alameri Energies 15 (21), 8008, 2022 | 14 | 2022 |
| Effect of Thermal Energy Storage Integration on Overall Nuclear Power Plant Efficiency M Ali, AK Alkaabi, SA Alameri, M Alrwashdeh Transactions of American Nuclear Society 121 (1), 1097-1098, 2019 | 13 | 2019 |
| Emirates Nuclear Technology Center, Khalifa University of Science and Technology, United Arab Emirates M Alrwashdeh American Nuclear Society 121, 1-5, 2019 | 12* | 2019 |
| 239Pu evaluation comparison study M Alrwashdeh Annals of Nuclear Energy 118, 313-316, 2018 | 11 | 2018 |
| U233 data evaluation for criticality study M Alrwashdeh, W Kan Journal of Nuclear Engineering and Radiation Science 2 (3), 034501, 2016 | 11* | 2016 |
| Covariance data evaluation for 233U M Alrwashdeh Applied Radiation and Isotopes 133, 105-110, 2018 | 10 | 2018 |
| Development of a code FITWR for nuclear cross section statistical analysis M Alrwashdeh, W Kan Annals of Nuclear Energy 70, 130-134, 2014 | 10 | 2014 |
| Nuclear data statistical treatment M Alrwashdeh, J Yu, A Abdalla, K Wang ASME. International Conference on Nuclear Engineering 5, V005T11A020, 2013 | 10 | 2013 |
| Homogenization of TRISO Fuel using Reactivity Equivalent Physical Transformation Method M Alrwashdeh, SA Alameri, AK Alkaabi, M Ali Transactions of American Nuclear Society 121 (1), 1521-1522, 2019 | 9 | 2019 |
| Two-dimensional full core analysis of IFBA-coated TRISO fuel particles in very high temperature reactors M Alrwashdeh, SA Alameri International Conference on Nuclear Engineering 83761, V001T05A014, 2020 | 8 | 2020 |
| Neutronic analysis of SiC/SiC sandwich cladding design in APR-1400 under normal operation conditions MM Alaleeli, SA Alameri, M Alrwashdeh Energies 15 (14), 5204, 2022 | 7 | 2022 |
| Sensitivity neutronic analysis of accident tolerant fuel concepts in APR1400 NT Alhattawi, M Alrwashdeh, SA Alameri, MM Alaleeli Journal of Nuclear Materials 582, 154487, 2023 | 6 | 2023 |
| Application of some turbulence models to simulate buoyancy-driven flow AAA Abdalla, J Yu, M Alrwashdeh International Conference on Nuclear Engineering 45943, V004T10A003, 2014 | 6 | 2014 |
| Evaluation review of the 250Cf neutron cross section M Alrwashdeh, S Alameri Applied Radiation and Isotopes 154, 108869, 2019 | 3 | 2019 |
| 233U Evaluation Comparison Study M Alrwashdeh, A Abdalla, K Wang International Conference on Nuclear Engineering 45943, V004T11A001, 2014 | 3 | 2014 |
| Nuclear Cross Section Statistical Analysis With FITWR Program M Alrwashdeh, A Abdalla, J Yu, K Wang Energy Development Frontier 2 (3), 89, 2013 | 3 | 2013 |
Saeed A. AlameriAssistant Professor, Nuclear Engineering, Khalifa University of Science and TechnologyVerified email at ku.ac.ae
