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Afshin Hedayat
Afshin Hedayat
Assistant Professor of the Reactor and Nuclear Safety Research School, Nuclear Science and Technology Research Institute (NSTRI)
在 aeoi.org.ir 的电子邮件经过验证
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引用次数
引用次数
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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
1072018
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
782009
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
662007
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
372009
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
292014
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
232014
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
222016
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
212017
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
212017
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
212016
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
172018
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
152020
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
152018
Developing and analyzing long-term fuel management strategies for an advanced Small Modular PWR
A Hedayat
Nuclear Engineering and Design 313, 190-213, 2017
142017
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
142016
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
122021
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
122020
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
112020
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
112016
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
102022
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