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Afshin Hedayat

Researcher at Amirkabir University of Technology

Publications -  27
Citations -  391

Afshin Hedayat is an academic researcher from Amirkabir University of Technology. The author has contributed to research in topics: Loss-of-coolant accident & Pressurized water reactor. The author has an hindex of 10, co-authored 24 publications receiving 279 citations.

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

TL;DR: In this paper, the authors provided a review of what has been done in the literature with regard to hydrogen generation in severe accidents of nuclear power plants and identified the literature gaps and underlined the need of developing a systematic hydrogen management strategy.
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Estimation of research reactor core parameters using cascade feed forward artificial neural networks

TL;DR: Final training and simulation results show that developed ANNs can be trained and estimate suggested core parameters of research reactors very quickly and improves effectively pattern optimization process of core reload program.
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Loss of coolant accident analyses on Tehran research reactor by RELAP5/MOD3.2 code

TL;DR: In this article, a loss of coolant accident (LOCA) in Tehran research reactor (TRR) is analyzed and two main loss of coolingant accidents are simulated and developed to analyze LOCA in TRR.
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Optimization of the core configuration design using a hybrid artificial intelligence algorithm for research reactors

TL;DR: A fast and effective hybrid artificial intelligence algorithm is introduced and developed to reach a Pareto optimal set and results show that introduced ANNs can be trained and estimate selected core parameters of a research reactor very quickly and improves effectively optimization process.
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Developing a practical optimization of the refueling program for ordinary research reactors using a modified simulated annealing method

TL;DR: In this paper, the authors proposed a 2D primary 2D annealing process followed up by a secondary re-annealing in fine 3D calculations to optimize the refueling cycle length and maximum irradiating thermal neutron flux.