Afshin Hedayat - Publications, H-index & Citations

Afshin Hedayat

Graduate University of Advanced Technology

14H指数

30论文数

553被引数

收录论文 14

发表时间

Application of artificial neural networks in the identification of nuclear power plant accident and transient 人工神经网络在核电站事故和瞬态识别中的应用

Progress in Nuclear Energy

IF3.2

2026-08-01

PREAI

Postekan, Hossein Farhang; Hedayat, Afshin

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 RELAP5 code and Computational Fluid Dynamic (CFD) modeling by ANSYS-FLUENT

PROGRESS IN NUCLEAR ENERGY

IF3.2

2022-08-01

PREAI

Hedayat, Afshin; Davari, Amin

Analysis of the gases distribution during a severe accident by coupling the MELCOR and FLUENT in WWER1000 containment

PROCESS SAFETY AND ENVIRONMENTAL PROTECTION

IF7.8

2022-06-01

PREAI

Gharari, R.; Kazeminejad, H.; Kojouri, N. Mataji; Hedayat, A.

Developing a robust and flexible smart tool to predict a full range Critical Heat Flux (CHF) in different LWRs by using deep learning Artificial Neural Networks (ANN) via parallel multi-processing

PROGRESS IN NUCLEAR ENERGY

IF3.2

2021-12-01

PREAI

Hedayat, Afshin

Study the effects of various parameters on hydrogen production in the WWER1000/V446

PROGRESS IN NUCLEAR ENERGY

IF3.2

2020-06-01

PREAI

Gharari, R.; Kazeminejad, H.; Kojouri, N. Mataji; Hedayat, A.; Vand, M. Hassan; Abadi, M. Nasiri Akbar; Safarzadeh, O.

The seismic analysis of the core structure in a pool-type material test reactor using 3-D finite difference method

PROGRESS IN NUCLEAR ENERGY

IF3.2

2018-07-01

PREAI

Hedayat, Afshin; Alborzi, Mohammad Javad

A review on hydrogen generation, explosion, and mitigation during severe accidents in light water nuclear reactors

INTERNATIONAL JOURNAL OF HYDROGEN ENERGY

IF8.3

2018-01-01

PREAI

Gharari, R.; Kazeminejad, H.; Kojouri, N. Mataji; Hedayat, A.

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 assemblies using MCNP and CFX

PROGRESS IN NUCLEAR ENERGY

IF3.2

2017-07-01

PREAI

Erfaninia, Ali; Hedayat, Afshin; Mirvakili, S. M.; Nematollahi, M. R.

Neutronic study of a new generation of the small modular pressurized water reactor using Monte-Carlo simulation

PROGRESS IN NUCLEAR ENERGY

IF3.2

2016-11-01

PREAI

Erfaninia, Ali; Hedayat, Afshin; Mirvakili, S. M.

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

PROGRESS IN NUCLEAR ENERGY

IF3.2

2016-04-01

PREAI

Hedayat, Afshin

Developing a practical optimization of the refueling program for ordinary research reactors using a modified simulated annealing method

PROGRESS IN NUCLEAR ENERGY

IF3.2

2014-09-01

PREAI

Hedayat, Afshin

Conceptual analyses of equilibrium conditions to determine a long-term fuel management strategy for research reactors

PROGRESS IN NUCLEAR ENERGY

IF3.2

2014-03-01

PREAI

Hedayat, Afshin

Estimation of research reactor core parameters using cascade feed forward artificial neural networks

PROGRESS IN NUCLEAR ENERGY

IF3.2

2009-08-01

PREAI

Hedayat, Afshin; Davilu, Hadi; Barfrosh, Ahmad Abdollahzadeh; Sepanloo, Kamran

Loss of coolant accident analyses on Tehran research reactor by RELAP5/MOD3.2 code

PROGRESS IN NUCLEAR ENERGY

IF3.2

2007-09-01

PREAI

Hedayat, Afshin; Davilu, Hadi; Jafari, Jalil

研究方向