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Mohsen Shayesteh

Observed names: M. Shayesteh, Mohsen shayesteh, Shayesteh, Mohsen, mohsen Shayesteh
ORCID: 0000-0002-5771-9708
Observed ORCID: 0000-0002-5771-9708
OpenAlex ID: A5081903573
Potential use of cold thermal energy storage systems for better efficiency and cost effectiveness
2010 · M.A. Ehyaei, A. Mozafari, et al. · Energy and Buildings · 42
Calculation of time-dependent neutronic parameters using Monte Carlo method
2009 · M. Shayesteh, M. Shahriari · Annals of Nuclear Energy · 16
Evaluation of Anticancer and Cytotoxic Effects of Genistein on PC3 Prostate Cell Line under Three-Dimensional Culture Medium
2022 · Seyedeh Masoumeh Khamesi, Mehdi Salehi Barough, et al. · Iranian Biomedical Journal · 12
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Thermal-hydraulic analysis of a novel design super critical water reactor with Al2O3 nanofluid as a coolant
2018 · M.H. Bahrevar, G. Jahanfarnia, et al. · The Journal of Supercritical Fluids · 12
Simulating and evaluating the pressurizer dynamic behavior in various sizes
2016 · Ghonche Baghban, Mohsen Shayesteh, et al. · Progress in Nuclear Energy · 7
The accumulator effects on in-vessel severe accident progression of a three loop PWR nuclear power plant in a SBLOCA without safety injection system
2017 · Mohsen Salehi, Mohsen Shayesteh · Annals of Nuclear Energy · 4
Combined Effect of Neutron Radiation and Curcumin on Breast Cancer Cells Cytotoxicity in 3D Culture Medium
2022 · Sajedeh zargan, Mehdi salehi borough, et al. · Iranian Biomedical Journal · 2
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Investigation of UO 2 fuel efficiency for ABV small modular reactor
2021 · Javad Karimi, Mohsen Shayesteh, et al. · Energy Sources Part A Recovery Utilization and Environmental Effects · 2
Core calculations for small modular reactor during burnup cycle
2021 · Javad Karimi, Mohsen Shayesteh, et al. · Energy Sources Part A Recovery Utilization and Environmental Effects · 2
Neutronic analysis of different patterns of ABV reactor core using low enrichment UO2 fuel
2021 · Javad Karimi, Mohsen Shayesteh, et al. · 2
Neutronic calculations for CANDU thorium systems using Monte Carlo techniques
2014 · M. Saldideh, M. Shayesteh, et al. · Chinese Physics C · 2
Investigation of Received Dose due to Cs-137 Release from a Hypothetical Accident for a Small Modular Reactor
2025 · Javad Karimi, Mohsen Shayesteh, et al. · Journal of Environmental Engineering · 1
Combined anticancer effects of neutron radiation and genistein on prostate cancer cells
2023 · Seyedeh Masoumeh Khamesi, Mehdi Salehi Barough, et al. · Journal of Radiation Research and Applied Sciences · 1
Simulation of protected and unprotected loss of flow transients in a WWER-1000 reactor based on the Drift-Flux Model
2017 · G. Baghban, M. Shayesteh, et al. · Kerntechnik · 1
Simulation and analysis of a WWER-1000 reactor under normal and transient conditions
2016 · Ghonche Baghban, Mohsen Shayesteh, et al. · Nuclear Technology and Radiation Protection · 1
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Simulation of Time Dependent Neutron Transport in Fission Reactors Using Monte-carlo Method
2007 · Mohsen Shayesteh, Shahriari Majid, et al. · Majallah-i ̒ulūm va funūn-i hastah/ī · 1
Thermo-neutronic analysis of natural circulation in the ABV small modular reactor under ocean-induced motions
2025 · Sayed Abolhasan Nourashrafeddin, Mohsen Shayesteh · Nuclear Engineering and Design
Investigation of Dynamic Neutron Radiography Capabilities in the Tehran Research Reactor by Designing an Experimental Set-Up
2025 · Majid Zamani, mohsen Shayesteh · SSRN Electronic Journal
Investigation of Dynamic Neutron Radiography Capabilities in the Tehran Research Reactor by Designing an Experimental Set-Up
2025 · Majid Zamani, mohsen Shayesteh · SSRN Electronic Journal
Designing a combined guide and investigating the role of collimator in neutron intensity uniformity
2024 · E. Tayebfard, M. Shayesteh, et al. · Annals of Nuclear Energy
Investigation of Radioisotopes Produced in the Core of a Navy Nuclear Reactor with Low- and High-Enriched Uranium Flues During One Cycle
2023 · Javad Karimi, Mohsen Shayesteh, et al. · Energy Sources Part A Recovery Utilization and Environmental Effects
Modeling the partial loss of coolant flow accident in the Super-critical water reactor
2021 · Mohammad Hossein Bahrevar, Gholamreza Jahanfarnia, et al.
Investigation of molten material retention during the large and small breaks LOCA and station blackout accident
2020 · Mohsen Salehi, Mohsen Shayesteh
Calculation of Neutron Flux and Spectrum in Three North Beam Tubes of Tehran Research Reactor for Bnct, by Mcnp
2013 · Z. Abd. Majid, Hossein Khalafi, et al. · Iranian Journal of Radiation Safety and Measurement
Simulation of Snow White Sampler in Order to Create a Native Nuclear Treaty System
2013 · M R Abasnezhad, M. Askari, et al. · ADST Journal
Works count: 31
Citation count: 108
H-index: 5
I10-index: 4
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