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M.H. Porhemmat

Observed names: M. H. Porhemmat, Mohamad Hadi Porhemmat, Mohammad Hadi Porhemmat, MohammadHadi Porhemmat, Mohammadhadi Porhemmat
ORCID: 0000-0002-1672-0518
Observed ORCID: 0000-0002-1672-0518
OpenAlex ID: A5003469150
PARCS cross-section library generator; part one: Development and verification
2014 · M.H. Porhemmat, K. Hadad, et al. · Progress in Nuclear Energy · 18
Verification and validation of the modular ray tracing MOC using the coupled forward-adjoint approach and application to C5G7 benchmark
2019 · M.H. Porhemmat, K. Hadad, et al. · Annals of Nuclear Energy · 6
Modular ray tracing in 2D whole core transport with MOC
2017 · M.H. Porhemmat, K. Hadad, et al. · Progress in Nuclear Energy · 6
Primary loop analysis for a PWR contains Passive Core Cooling System; LOCA and clad rising temperature
2016 · M.H. Porhemmat, F. Faghihi, et al. · Annals of Nuclear Energy · 6
SARCS cross section library generator: Part two: Fast and quasi transients evaluations
2015 · K. Hadad, M.H. Porhemmat · Progress in Nuclear Energy · 4
Assessment of critical heat flux (CHF) on irradiated and non-irradiated nano-composite surfaces
2025 · Aref Rahimian, MohammadHadi Porhemmat · Nuclear Engineering and Design · 2
Evaluation of time dependent neutron transport algorithms using 2D modular ray tracing MOC
2023 · Sahar Ghaseminejad, Kamal Hadad, et al. · Progress in Nuclear Energy · 2
Improved memory management for solving neutron transport via a novel Modular Ray Tracing (MRT) approach embedded in parallel method of characteristic (MOC) framework
2021 · Mohammadhadi Porhemmat, Mojtaba Mahzoon, et al. · Progress in Nuclear Energy · 2
Developing 3D neutron transport kernel for heterogeneous structures in an improved method of characteristic (MOC) framework
2020 · M.H. Porhemmat, K. Hadad, et al. · Progress in Nuclear Energy · 1
A reduced-order primary model for modern PWR primary loop analysis - Part I: RELAP5 benchmarking
2015 · Mohamad Hadi Porhemmat, Farshad Faghihi, et al. · International Journal of Nuclear Energy Science and Technology · 1
Comprehensive computational fluid dynamic assessment of shrouded nozzles for radioactive aerosol sampling: Sensitivity analysis and validation
2026 · R. Gharari, R. Ahangari, et al. · Progress in Nuclear Energy
Augmentation of the neutronic safety aspect of high-density fuel research reactor using new control element design
2025 · Mohammad Hadi Porhemmat, Mostafa Hassanzadeh, et al. · Kerntechnik
Evaluation of various calculational models of FA containing burnable absorber rod in the VVER-1000
2025 · Sahar Ghaseminejad, Mohammadhadi Porhemmat · Kerntechnik
Development and Implementation of 3D Algorithm of Neutron Transport Solution Via 2D(MOC) /1D(NEM) Fusion Method
2024 · M. H. Porhemmat, A. Lashkari · Journal of Nuclear Research and Applications
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Works count: 14
Citation count: 48
H-index: 4
I10-index: 1
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