フォロー
Hassan Esmaili
Hassan Esmaili
Nuclear Science and Technology Research Institute (NSTRI)
確認したメール アドレス: aeoi.org.ir
タイトル
引用先
引用先
Subchannel analysis of annular fuel assembly using the preconditioned Jacobian-free Newton Krylov methods
H Esmaili, H Kazeminejad, H Khalafi, SM Mirvakili
Annals of Nuclear Energy 146, 107616, 2020
182020
Prediction of temperature distribution in annular fuels using orthogonal collocation method
H Esmaili, H Kazeminejad, H Khalafi
Annals of Nuclear Energy 134, 77-87, 2019
72019
Development of subchannel thermal-hydraulic analysis code for dual cooled annular fuel
AH Saffari, H Esmaili
Progress in Nuclear Energy 150, 104298, 2022
62022
Assessment of the research reactors in opposition to severe accidents
R Gharari, R Ahangari, H Esmaili, E Hasanifard
Nuclear Engineering and Design 415, 112716, 2023
12023
New insights to containment management in TRR during severe accident by spray and fan cooler measures
R Gharari, R Ahangari, H Esmaili
Progress in Nuclear Energy 164, 104897, 2023
12023
Development of preconditioners for numerical simulation of two-phase flow using Krylov subspace methods
H Esmaili, H Kazeminejad, R Ahangari, E Boustani
Progress in Nuclear Energy 139, 103852, 2021
12021
Neutronic and thermal-hydraulic assessment of the TRR with new core designed based on tubular fuels
R Gharari, F Khoshahval, M Hasanzadeh, MA Mozaffari, MA Amirkhani, ...
Kerntechnik 88 (6), 670-686, 2023
2023
Thermal hydraulic analysis of a tubular fuel assembly in the normal operating condition of Tehran Research Reactor core
M Hasanzadeh, M Amin Mozafari, F Khoshahval, R Gharari, H Esmaeili
Journal of Nuclear Science, Engineering and Technology (JONSAT) 43 (2), 114-124, 2022
2022
Uncertainty analysis of a typical research reactor performance for radioisotope production
E Boustani, M Hasanzadeh, H Esmaeili
Nuclear Engineering and Design 400, 112058, 2022
2022
Fully implicit numerical simulation of subcooled flow boiling in a vertical channel using higher order schemes
H Esmaili, H Kazeminejad
1st International & 28th National Conference on Nuclear Science and …, 2022
2022
Simulation of two-phase flow drift flux model in a vertical channel using Newton–Krylov method
H Esmaili, H Kazeminejad, H Khalafi, SM Mirvakili
Journal of Nuclear Science, Engineering and Technology (JONSAT) 42 (1), 1-10, 2021
2021
Safety analysis of total LOCA in a fuel plate research reactor
E Boustani, S Khakshournia, Esmaili, H.
6th International Reliability and Safety Engineering Conference, IRSEC2020 …, 2021
2021
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