A review on hydrogen generation, explosion, and mitigation during severe accidents in light water nuclear reactors R Gharari, H Kazeminejad, NM Kojouri, A Hedayat International Journal of Hydrogen Energy 43 (4), 1939-1965, 2018 | 107 | 2018 |
Estimation of research reactor core parameters using cascade feed forward artificial neural networks A Hedayat, H Davilu, AA Barfrosh, K Sepanloo Progress in Nuclear Energy 51 (6-7), 709-718, 2009 | 78 | 2009 |
Loss of coolant accident analyses on Tehran research reactor by RELAP5/MOD3. 2 code A Hedayat, H Davilu, J Jafari Progress in Nuclear Energy 49 (7), 511-528, 2007 | 66 | 2007 |
Optimization of the core configuration design using a hybrid artificial intelligence algorithm for research reactors A Hedayat, H Davilu, AA Barfrosh, K Sepanloo Nuclear engineering and design 239 (12), 2786-2799, 2009 | 37 | 2009 |
Developing a practical optimization of the refueling program for ordinary research reactors using a modified simulated annealing method A Hedayat Progress in Nuclear Energy 76, 191-205, 2014 | 29 | 2014 |
Conceptual analyses of equilibrium conditions to determine a long-term fuel management strategy for research reactors A Hedayat Progress in Nuclear Energy 71, 61-72, 2014 | 23 | 2014 |
Neutronic study of a new generation of the small modular pressurized water reactor using Monte-Carlo simulation A Erfaninia, A Hedayat, SM Mirvakili Progress in Nuclear Energy 93, 218-230, 2016 | 22 | 2016 |
Simulation and transient analyses of a complete passive heat removal system in a downward cooling pool-type material testing reactor against a complete station blackout and … A Hedayat Nuclear Engineering and Technology 49 (5), 953-967, 2017 | 21 | 2017 |
Neutronic-thermal hydraulic coupling analysis of the fuel channel of a new generation of the small modular pressurized water reactor including hexagonal and square fuel … A Erfaninia, A Hedayat, SM Mirvakili, MR Nematollahi Progress in Nuclear Energy 98, 213-227, 2017 | 21 | 2017 |
Benchmarking verification of the control rod effects on the MTR core parameters using the MTR-PC and MCNP codes throughout 3D core modeling and rod-drop experiment A Hedayat Progress in Nuclear Energy 88, 183-190, 2016 | 21 | 2016 |
Self-pressurization analysis of the natural circulation integral nuclear reactor using a new dynamic model AF Pilehvar, MH Esteki, A Hedayat, GR Ansarifar Nuclear engineering and technology 50 (5), 654-664, 2018 | 17 | 2018 |
Assessment of new severe accident mitigation systems on containment pressure of the WWER1000/V446 R Gharari, H Kazeminejad, NM Kojouri, A Hedayat, MH Vand Annals of Nuclear Energy 148, 107691, 2020 | 15 | 2020 |
Simulation and conceptual analyses of a stable natural core cooling system in an integrated small modular PWR SK Moghanaki, A Hedayat Nuclear Engineering and Design 332, 357-373, 2018 | 15 | 2018 |
Developing and analyzing long-term fuel management strategies for an advanced Small Modular PWR A Hedayat Nuclear Engineering and Design 313, 190-213, 2017 | 14 | 2017 |
Developing a safe and high performance fuel management optimization for MTRs using stochastic knowledge base searches A Hedayat Annals of Nuclear Energy 90, 157-174, 2016 | 14 | 2016 |
Application of a severe accident code to the sensitivity and uncertainty analysis of hydrogen production in the WWER1000/V446 R Gharari, H Kazeminejad, NM Kojouri, A Hedayat, MH Vand Annals of Nuclear Energy 152, 108018, 2021 | 12 | 2021 |
Stability analysis and parametric study of natural circulation integrated self-pressurized water reactor AF Pilehvar, MH Esteki, GR Ansarifar, A Hedayat Annals of Nuclear Energy 139, 107279, 2020 | 12 | 2020 |
Study the effects of various parameters on hydrogen production in the WWER1000/V446 R Gharari, H Kazeminejad, NM Kojouri, A Hedayat, MH Vand, MNA Abadi, ... Progress in Nuclear Energy 124, 103370, 2020 | 11 | 2020 |
Conceptual analyses of neutronic and equilibrium refueling parameters to develop a cost-effective multi-purpose pool-type research reactor using WIMSD and CITVAP codes A Hedayat Nuclear Engineering and Design 309, 236-253, 2016 | 11 | 2016 |
Feasibility study to increase the reactor power at natural convection mode in Tehran Research Reactor (TRR) through a hybrid thermal-hydraulic simulation and analysis using the … A Hedayat, A Davari Progress in Nuclear Energy 150, 104285, 2022 | 10 | 2022 |