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F
F. Faghihi
Shiraz University
18
H指数
69
论文数
679
被引数
0
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23
发表时间
发表时间
IF
被引数
DYSN: Dynamics simulator for the NuScale SMR - A mathematical framework for transient analysis
PROGRESS IN NUCLEAR ENERGY
IF
3.2
2024-05-01
0
PRE
AI
Fakhraei, A.; Faghihi, F.; Mohammadi, M.; Rabiee, A.
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Gamma dose rate determination of TRR irradiated fuel assemblies
TRR辐照燃料组件的 γ 剂量率测定
PROGRESS IN NUCLEAR ENERGY
IF
3.2
2021-12-01
1
PRE
AI
Bagheri, S.; Khalafi, H.; Faghihi, F.; Ezzati, A.; Keyvani, M.; Ghods, H.
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Investigation of ex-vessel core catcher for SBO accident in VVER-1000/V528 containment using MELCOR code
NUCLEAR SCIENCE AND TECHNIQUES
IF
3.8
2021-04-21
10
PRE
AI
Salari, Farhad; Rabiee, Ataollah; Faghihi, Farshad
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Coolant flow rate instability during extended station blackout accident in NuScale SMR: Two approaches for improving flow stability
PROGRESS IN NUCLEAR ENERGY
IF
3.2
2021-01-01
9
PRE
AI
Fakhraei, A.; Faghihi, F.; Rabiee, A.; Safarinia, M.
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Innovative passive management of the Station Black-Out accident for VVER1000/V446 NPP and development of its emergency operating procedures
PROGRESS IN NUCLEAR ENERGY
IF
3.2
2020-08-01
6
PRE
AI
Hosseini, M. M.; Faghihi, F.; Pirouzmand, A.; Rabiee, A.
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A new fuel depletion code based on group-wised energy Bateman ODEs; SUDEPLET code for point-like PWR core
PROGRESS IN NUCLEAR ENERGY
IF
3.2
2020-01-01
0
PRE
AI
Faghihi, F.; Bahrami, A. A.; Nematollahi, M. R.; Mojassami, S.
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Core designing of the newly proposed (U+Gd)O2 FAs in the VVERs core and comparison with current UO2FAs
ALEXANDRIA ENGINEERING JOURNAL
IF
6.8
2019-06-01
3
OA
AI
Faghihi, F.; Roosta, F.; Ghaemi, S.; Bagheri, S.
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Core designing of a new type of TVS-2M FAs: neutronics and thermal-hydraulics design basis limits
FRONTIERS IN ENERGY
IF
6.2
2018-09-26
3
PRE
AI
Ghaemi, Saeed; Faghihi, Farshad
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A novel multi-objective optimization method, imperialist competitive heck for algorithm, for fuel loading pattern of nuclear reactors
PROGRESS IN NUCLEAR ENERGY
IF
3.2
2018-09-01
21
PRE
AI
Akbari, R.; Abbasi, M.; Faghihi, F.; Mirvakili, S. M.; Mokhtari, J.
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Design and optimization of the new LEU MNSR for neutron radiography using thermal column to upgrade thermal flux
PROGRESS IN NUCLEAR ENERGY
IF
3.2
2017-09-01
20
PRE
AI
Mokhtari, J.; Faghihi, F.; Khorsandi, J.
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Conceptual design study of the low power and LEU medical reactor for BNCT using in-tank fission converter to increase epithermal flux
PROGRESS IN NUCLEAR ENERGY
IF
3.2
2017-03-01
20
PRE
AI
Mokhtari, J.; Faghihi, F.; Khorsandi, J.; Hadad, K.
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Assessment of thermal hydraulics parameters of the VVER-1000 during transient conditions
INTERNATIONAL JOURNAL OF HYDROGEN ENERGY
IF
8.3
2016-05-01
6
PRE
AI
Bagheri, Somayeh; Faghihi, Farshad; Nematollahi, Mohammad Reza; Behzadinejad, Behnam
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Safety analysis of LBLOCA in BDBA scenarios for the Bushehr's VVER-1000 nuclear power plant
PROGRESS IN NUCLEAR ENERGY
IF
3.2
2016-04-01
23
PRE
AI
Pirouzmand, Ahmad; Ghasemi, Armin; Faghihi, Farshad
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Neutronics and sub-channel thermal-hydraulics analysis of the Iranian VVER-1000 fuel bundle
PROGRESS IN NUCLEAR ENERGY
IF
3.2
2016-03-01
26
PRE
AI
Faghihi, F.; Mirvakili, S. M.; Safaei, S.; Bagheri, S.
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Study on the recently proposed direct S-CO2 and helium-cooled GCFR: Size of vessel, power conversion, and reactivity coefficients
PROGRESS IN NUCLEAR ENERGY
IF
3.2
2015-05-01
4
PRE
AI
Mohammadi, M. M.; Faghihi, F.; Pirouzmand, A.; Rabiee, A.
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PARCS cross-section library generator; part one: Development and verification
PROGRESS IN NUCLEAR ENERGY
IF
3.2
2015-01-01
15
PRE
AI
Porhemmat, M. H.; Hadad, K.; Faghihi, F.
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Prompt and power reactivity coefficients for the next generation VVER-1000 reactor including hexagonal assemblies and annular fuels
PROGRESS IN NUCLEAR ENERGY
IF
3.2
2012-11-01
16
PRE
AI
Nia, A. Erfani; Faghihi, F.; Hadad, K.
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Two safety coefficients for a typical 13 x 13 annular fuel assembly
PROGRESS IN NUCLEAR ENERGY
IF
3.2
2011-04-01
13
PRE
AI
Faghihi, F.; Nezhad, M. Saidi
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Modified COBRA-EN code to investigate thermal-hydraulic analysis of the Iranian VVER-1000 core
PROGRESS IN NUCLEAR ENERGY
IF
3.2
2010-08-01
42
PRE
AI
Arshi, S. Safaei; Mirvakili, S. M.; Faghihi, F.
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Level-1 probability safety assessment of the Iranian heavy water reactor using SAPHIRE software
RELIABILITY ENGINEERING & SYSTEM SAFETY
IF
11
2008-10-01
17
PRE
AI
Faghihi, F.; Ramezani, E.; Yousefpour, F.; Mirvakili, S. M.
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研究方向
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合作学者
合作期刊
M
Mohammad Mohammadi
H 指数: 36 · 论文数: 236
R
Reza Akbari
H 指数: 21 · 论文数: 112
K
Kamal Hadad
H 指数: 20 · 论文数: 126
J
J. Mokhtari
H 指数: 19 · 论文数: 62
H
H. Khalafi
H 指数: 17 · 论文数: 118
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