Aarabi Jeshvaghani, peyman
Prediction of Air and Water Flow-Rates Independent of Flow Regimes Using Gamma-Ray Attenuation Technique and Artificial Neural Network [Volume 1, Issue 1, 2022, Pages 49-54]
Abedi Masir, Majid
Study of temperature effect of wall on gaseous diffusion separation using direct simulation Monte Carlo method (DSMC) [Volume 1, Issue 2, 2022, Pages 53-63]
Adeli, Ruhollah
Introducing a polymeric setup with maximum thermal neutron removal for neutron radiographic shutter design [Volume 1, Issue 2, 2022, Pages 47-52]
Alahyarizadeh, Ghasem
Study of temperature effect of wall on gaseous diffusion separation using direct simulation Monte Carlo method (DSMC) [Volume 1, Issue 2, 2022, Pages 53-63]
B
Bagheroskouei, F
A comprehensive review of radiation models in the space environment [Volume 2, Issue 2, 2023]
D
Dehghanizadeh, M
Thermo-Mechanical Analysis of VVER-1000 Fuel Rods during Loss of Coolant Accident using FRAPTRAN code [Volume 1, Issue 1, 2022, Pages 1-8]
F
Feghhi, Seyed Amir Hossein
Prediction of Air and Water Flow-Rates Independent of Flow Regimes Using Gamma-Ray Attenuation Technique and Artificial Neural Network [Volume 1, Issue 1, 2022, Pages 49-54]
G
Ghanbari, Ebrahim
Assessment of Proposed Sites for the Establishment of Fars Research Reactor [Volume 2, Issue 1, 2023, Pages 64-71]
H
Hosseini, Seyed Ali
Design, Simulation and Evaluation of Pressure Control System in a High-pressure Research Test loop [Volume 1, Issue 4, 2023, Pages 1-9]
Hosseinllu, Majid
Conceptual Design and reactivity control of long-life and LEU soluble boron free
Hexagonal Fuel Assembly [Volume 1, Issue 4, 2023, Pages 43-52]
Hosseinllu, Majid
Simulating and analysis of neutronic parameters of a Soluble-Boron-Free
marine baise reactor core [(Articles in Press)]
Hosseinpour Khanmiri, Mohammad
The Alpha-Spectroscopy of U and Th Isotopes of the Saghand Ore Anomaly 2 and the Surface Part Anomaly 1 [Volume 1, Issue 3, 2022, Pages 14-25]
J
Jahanfarnia, Gh
Thermo-Mechanical Analysis of VVER-1000 Fuel Rods during Loss of Coolant Accident using FRAPTRAN code [Volume 1, Issue 1, 2022, Pages 1-8]
Jahanfarnia, Gholam Reza
Fire simulation in the control room of Bushehr nuclear power plant by CFAST software [Volume 1, Issue 4, 2023, Pages 10-14]
K
Karimi-Sabet, Javad
Modeling and simulation a molecular pump of a gas centrifuge with analytical methods of Sawada and Sickafus and its three-dimensional simulation with DSMC method [Volume 1, Issue 3, 2022, Pages 52-64]
Khameh, Hossein
Simulation and investigation of neutronic parameters of Tehran research reactor core using probabilistic codes [(Articles in Press)]
Kheradmand, mohsen
Thermo-Mechanical Analysis of VVER-1000 Fuel Rods during Loss of Coolant Accident using FRAPTRAN code [Volume 1, Issue 1, 2022, Pages 1-8]
Khorsandi, Majid
Prediction of Air and Water Flow-Rates Independent of Flow Regimes Using Gamma-Ray Attenuation Technique and Artificial Neural Network [Volume 1, Issue 1, 2022, Pages 49-54]
M
Mallah, Mohammad Hassan
Modeling and simulation of gas behavior with DSMC method and calculating the separation parameters inside a gas centrifuge [Volume 1, Issue 3, 2022, Pages 26-35]
Mallah, Mohhammad hasan
Modeling and simulation a molecular pump of a gas centrifuge with analytical methods of Sawada and Sickafus and its three-dimensional simulation with DSMC method [Volume 1, Issue 3, 2022, Pages 52-64]
Mansouri, Masoud
Fire simulation in the control room of Bushehr nuclear power plant by CFAST software [Volume 1, Issue 4, 2023, Pages 10-14]
Mojab, Sahar
Fire simulation in the control room of Bushehr nuclear power plant by CFAST software [Volume 1, Issue 4, 2023, Pages 10-14]
Mokhtari, Javad
Validation of deterministic and probabilistic methods for calculating kinetic parameters with experimental reactivity in new configuration of HWZPR reactor core [Volume 1, Issue 1, 2022, Pages 9-23]
N
Najafi, Alireza
Success Criteria Analysis of Steam Line Break for a Typical Two-loop Westinghouse PWR [Volume 2, Issue 2, 2023]
Nazari, Masoud
Solving Multigroup, One-dimensional Neutron Transport Equation Using SDP1 Method [Volume 2, Issue 1, 2023, Pages 18-36]
Nematollahi, mohammadreza
Investigation of reflector role in neutronic and control parameters of small modular reactor core using Monte Carlo modeling [Volume 2, Issue 1, 2023, Pages 11-17]
Nikrooy, Hamid
Level 1 Probabilistic Safety Assessment at Zero Power Heavy Water Reactor (HWZPR) [(Articles in Press)]
Noori, Ehsan
Measurement of Emitted Neutron and Deuteron Energies in a Dense Plasma Focus Device [Volume 2, Issue 2, 2023]
Norouzi, Ali
Modeling and simulation of gas behavior with DSMC method and calculating the separation parameters inside a gas centrifuge [Volume 1, Issue 3, 2022, Pages 26-35]
R
Rabiee, َAtaollah
Design of an optimized PID control system for Tehran research reactor based on TLBO algorithm [Volume 1, Issue 3, 2022, Pages 1-13]
Raeisdana, Amir
Measurement of Emitted Neutron and Deuteron Energies in a Dense Plasma Focus Device [Volume 2, Issue 2, 2023]
Rasouli, Chapar
Measurement of Emitted Neutron and Deuteron Energies in a Dense Plasma Focus Device [Volume 2, Issue 2, 2023]
Rezaee Ebrahim Saraee, Khadijeh
Thermoluminescence properties study of magnesium oxide doped with lanthanides and lithium under gamma irradiation for dosimetric applications [Volume 1, Issue 2, 2022, Pages 1-12]
Rokrok, Behrouz
Introducing a polymeric setup with maximum thermal neutron removal for neutron radiographic shutter design [Volume 1, Issue 2, 2022, Pages 47-52]
S
Sadegh Noe doost, Amir
Proposed a mathematical model to investigate the dynamic behavior of a small modular reactor core with natural circulation flow by Simulink toolbox of Matlab software [Volume 2, Issue 1, 2023, Pages 56-64]
Sadegh Noe doost, Amir
Investigation of Xenon concentration effect on the thermal conductivity of the gap between fuel and cladding in a PWR reactor [Volume 2, Issue 2, 2023]
Sadighzadeh, Asghar
Measurement of Emitted Neutron and Deuteron Energies in a Dense Plasma Focus Device [Volume 2, Issue 2, 2023]
Safdari, Jaber
Modeling and simulation of gas behavior with DSMC method and calculating the separation parameters inside a gas centrifuge [Volume 1, Issue 3, 2022, Pages 26-35]
Safdari, Jaber
Modeling and simulation a molecular pump of a gas centrifuge with analytical methods of Sawada and Sickafus and its three-dimensional simulation with DSMC method [Volume 1, Issue 3, 2022, Pages 52-64]
Shirani, Amir Saeed
Success Criteria Analysis of Steam Line Break for a Typical Two-loop Westinghouse PWR [Volume 2, Issue 2, 2023]
Shoorian, s
A comprehensive review of radiation models in the space environment [Volume 2, Issue 2, 2023]
T
Taghizadeh, leili
Validation of deterministic and probabilistic methods for calculating kinetic parameters with experimental reactivity in new configuration of HWZPR reactor core [Volume 1, Issue 1, 2022, Pages 9-23]
Y
Yousefi-Nasab, Sadegh
Modeling and simulation of gas behavior with DSMC method and calculating the separation parameters inside a gas centrifuge [Volume 1, Issue 3, 2022, Pages 26-35]
Yousefi-Nasab, Sadegh
Modeling and simulation a molecular pump of a gas centrifuge with analytical methods of Sawada and Sickafus and its three-dimensional simulation with DSMC method [Volume 1, Issue 3, 2022, Pages 52-64]
Z
Zangian, Mehdi
Validation of deterministic and probabilistic methods for calculating kinetic parameters with experimental reactivity in new configuration of HWZPR reactor core [Volume 1, Issue 1, 2022, Pages 9-23]
Zare Ganjaroodi, Saeed
Thermo-Hydraulic Analysis of Passive Heat Removal System (PHRS) in VVER-1000 Nuclear Reactor Using RELAP5 Code [Volume 1, Issue 4, 2023, Pages 32-42]
Zare Ganjaroodi, Saeed
Investigation of the dynamic behavior of the Isfahan miniature neutron source reactor core during the reactivity injection accident [Volume 2, Issue 2, 2023]
Zare Ganjaroodi, Saeed
Simulation and investigation of neutronic parameters of Tehran research reactor core using probabilistic codes [(Articles in Press)]
Zare Ganjaroodi, Saeed
Level 1 Probabilistic Safety Assessment at Zero Power Heavy Water Reactor (HWZPR) [(Articles in Press)]
Zarifi, Ehsan
Fire simulation in the control room of Bushehr nuclear power plant by CFAST software [Volume 1, Issue 4, 2023, Pages 10-14]
Zarifi, Ehsan
Investigation of the dynamic behavior of the Isfahan miniature neutron source reactor core during the reactivity injection accident [Volume 2, Issue 2, 2023]
Zarifi, Ehsan
Simulation and investigation of neutronic parameters of Tehran research reactor core using probabilistic codes [(Articles in Press)]
Zarifi, Ehsan
Level 1 Probabilistic Safety Assessment at Zero Power Heavy Water Reactor (HWZPR) [(Articles in Press)]