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, ŮŽAtaollah 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)]