Harmonizing nuclear and renewable energy: Case studies JH Kim, SA Alameri International Journal of Energy Research 44 (10), 8053-8061, 2020 | 33 | 2020 |
Preliminary neutronic analysis of alternative cladding materials for APR-1400 fuel assembly M Alrwashdeh, SA Alameri Nuclear Engineering and Design 384, 111486, 2021 | 29 | 2021 |
Prismatic-core advanced high temperature reactor and thermal energy storage coupled system–A preliminary design SA Alameri, JC King, AK Alkaabi, Y Addad Nuclear Engineering and Technology 52 (2), 248-257, 2020 | 26 | 2020 |
A coupled nuclear reactor thermal energy storage system for enhanced load following operation SA Alameri, JC King 2013 International Nuclear Atlantic Conference - INAC 2013 45 (25), 12, 2013 | 26 | 2013 |
Overall efficiency analysis of an innovative load-following nuclear power plant-thermal energy storage coupled cycle M Ali, AK Alkaabi, SA Alameri, Y Addad International Journal of Exergy 36 (1), 98-122, 2021 | 25 | 2021 |
Fundamentals of nuclear reactors SA Alameri, AK Alkaabi Nuclear Reactor Technology Development and Utilization, 27-60, 2020 | 25 | 2020 |
SiC and FeCrAl as potential cladding materials for APR-1400 neutronic analysis M Alrwashdeh, SA Alameri Energies 15 (10), 3772, 2022 | 23 | 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 | 23 | 2020 |
Chromium-coated zirconium cladding neutronics impact for APR-1400 reactor core M Alrwashdeh, SA Alameri Energies 15 (21), 8008, 2022 | 19 | 2022 |
Emerging areas of nuclear power applications JH Kim, MM Song, SA Alameri Nuclear Engineering and Design 354, 110183, 2019 | 18 | 2019 |
Effects of ATF cladding properties on PWR responses to an SBO accident: A sensitivity analysis A Alraisi, Y Yi, S Lee, SA Alameri, M Qasem, CY Paik, C Jang Annals of Nuclear Energy 165, 108784, 2022 | 17 | 2022 |
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 | 17 | 2021 |
Convergence studies using method of characteristics solver for the Reduced-Moderation Water Reactor model SB Alam, B Almutairi, D Kumar, CS Goodwin, SA Alameri Nuclear Science and Engineering, 2019 | 15 | 2019 |
Effect of thermal energy storage integration on overall nuclear power plant efficiency M Ali, AK Alkaabi, SA Alameri, M Alrwashdeh Transactions 121 (1), 1097-1098, 2019 | 13 | 2019 |
Assessment of a Nuclear Reactor-Thermal Energy Storage Coupled System SA Alameri, AK Alkaabi 2018 ANS Annual Meeting, Philadelphia, Pennsylvania, 2018 | 12 | 2018 |
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 | 10 | 2023 |
Thermal analysis of baffle jetting in fuel rod assembly M Ali, AK Alkaabi, SA Alameri, I Afgan Physics of Fluids 34 (11), 2022 | 10 | 2022 |
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 | 10 | 2022 |
Homogenization of TRISO Fuel using Reactivity Equivalent Physical Transformation Method M Alrwashdeh, SA Alameri, AK Alkaabi, M Ali Transactions 121 (1), 1521-1522, 2019 | 10 | 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 | 9 | 2020 |