AC&DC Voltage
Quadrupole simulation in a mass spectrometer [Volume 1, Issue 2, 2022-2023, Pages 27-38]
Adjoint flux
Validation of deterministic and probabilistic methods for calculating kinetic parameters with experimental reactivity in new configuration of HWZPR reactor core [Volume 1, Issue 1, 2022-2023, Pages 9-23]
Alpha -Spectroscopy
The Alpha-Spectroscopy of U and Th Isotopes of the Saghand Ore Anomaly 2 and the Surface Part Anomaly 1 [Volume 1, Issue 3, 2022-2023, Pages 14-25]
Artificial Neural Networks
Feasibility study of 99Mo radioisotope production using uranium molten salt target irradiation by 30 Mev proton Cyclotron [Volume 1, Issue 1, 2022-2023, Pages 36-48]
Artificial Neural Networks
Prediction of Air and Water Flow-Rates Independent of Flow Regimes Using Gamma-Ray Attenuation Technique and Artificial Neural Network [Volume 1, Issue 1, 2022-2023, Pages 49-54]
B
BNPP
Simulation and Analysis of the Coolant Mixing Test within the Reactor Pressure Vessel of BNPP Using ANSYS CFX 18.0 [Volume 2, Issue 1, 2023-2024, Pages 1-10]
BNPP-1
Fire simulation in the control room of Bushehr nuclear power plant by CFAST software [Volume 1, Issue 4, 2022-2023, Pages 10-14]
C
Calculating the Weight Percent of Uranium
The Alpha-Spectroscopy of U and Th Isotopes of the Saghand Ore Anomaly 2 and the Surface Part Anomaly 1 [Volume 1, Issue 3, 2022-2023, Pages 14-25]
Caramel Fuel
Redesign of Tehran Research Reactor Core by using UO2 Plate Fuel [Volume 2, Issue 2, 2023-2024]
CAREM-25
Investigation of reflector role in neutronic and control parameters of small modular reactor core using Monte Carlo modeling [Volume 2, Issue 1, 2023-2024, Pages 11-17]
Cermet fuel
simulation of thermal conductivity and heat transfer of cermet fuel using Fluent software [Volume 1, Issue 3, 2022-2023, Pages 44-51]
CFAST code
Fire simulation in the control room of Bushehr nuclear power plant by CFAST software [Volume 1, Issue 4, 2022-2023, Pages 10-14]
CFX
Simulation and Analysis of the Coolant Mixing Test within the Reactor Pressure Vessel of BNPP Using ANSYS CFX 18.0 [Volume 2, Issue 1, 2023-2024, Pages 1-10]
COMSOL
Quadrupole simulation in a mass spectrometer [Volume 1, Issue 2, 2022-2023, Pages 27-38]
Coolant mixing
Simulation and Analysis of the Coolant Mixing Test within the Reactor Pressure Vessel of BNPP Using ANSYS CFX 18.0 [Volume 2, Issue 1, 2023-2024, Pages 1-10]
Coolant temperature distribution
Simulation and Analysis of the Coolant Mixing Test within the Reactor Pressure Vessel of BNPP Using ANSYS CFX 18.0 [Volume 2, Issue 1, 2023-2024, Pages 1-10]
Core damage frequency
Level 1 Probabilistic Safety Assessment at Zero Power Heavy Water Reactor (HWZPR) [(Articles in Press)]
Cosmic rays
A comprehensive review of radiation models in the space environment [Volume 2, Issue 2, 2023-2024]
Coupling of Aspen HYSYS with MATLAB Simulink
Design, Simulation and Evaluation of Pressure Control System in a High-pressure Research Test loop [Volume 1, Issue 4, 2022-2023, Pages 1-9]
D
D-D Fusion Reactions
Measurement of Emitted Neutron and Deuteron Energies in a Dense Plasma Focus Device [Volume 2, Issue 2, 2023-2024]
Detector counts
Feasibility study of 99Mo radioisotope production using uranium molten salt target irradiation by 30 Mev proton Cyclotron [Volume 1, Issue 1, 2022-2023, Pages 36-48]
Deterministic Safety Analysis
Success Criteria Analysis of Steam Line Break for a Typical Two-loop Westinghouse PWR [Volume 2, Issue 2, 2023-2024]
Deterministic Safety Assessment
Fire simulation in the control room of Bushehr nuclear power plant by CFAST software [Volume 1, Issue 4, 2022-2023, Pages 10-14]
Deuterium Beam Energy
Measurement of Emitted Neutron and Deuteron Energies in a Dense Plasma Focus Device [Volume 2, Issue 2, 2023-2024]
Direct simulation Monte Carlo method
Study of temperature effect of wall on gaseous diffusion separation using direct simulation Monte Carlo method (DSMC) [Volume 1, Issue 2, 2022-2023, Pages 53-63]
Dittus-Boelter
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, 2023-2024, Pages 56-64]
Dosimetry
Thermoluminescence properties study of magnesium oxide doped with lanthanides and lithium under gamma irradiation for dosimetric applications [Volume 1, Issue 2, 2022-2023, Pages 1-12]
Double-Spherical Harmonics Method
Solving Multigroup, One-dimensional Neutron Transport Equation Using SDP1 Method [Volume 2, Issue 1, 2023-2024, Pages 18-36]
DSA
Fire simulation in the control room of Bushehr nuclear power plant by CFAST software [Volume 1, Issue 4, 2022-2023, Pages 10-14]
DSMC
Modeling and simulation of gas behavior with DSMC method and calculating the separation parameters inside a gas centrifuge [Volume 1, Issue 3, 2022-2023, Pages 26-35]
DSMC
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, 2022-2023, Pages 52-64]
Dynamic
Investigation of the dynamic behavior of the Isfahan miniature neutron source reactor core during the reactivity injection accident [Volume 2, Issue 2, 2023-2024]
E
Effective thermal conductivity
simulation of thermal conductivity and heat transfer of cermet fuel using Fluent software [Volume 1, Issue 3, 2022-2023, Pages 44-51]
Enthalpy Rise Method
Investigation of Xenon concentration effect on the thermal conductivity of the gap between fuel and cladding in a PWR reactor [Volume 2, Issue 2, 2023-2024]
Epoxy
Introducing a polymeric setup with maximum thermal neutron removal for neutron radiographic shutter design [Volume 1, Issue 2, 2022-2023, Pages 47-52]
F
Finite Element Method
Solving Multigroup, One-dimensional Neutron Transport Equation Using SDP1 Method [Volume 2, Issue 1, 2023-2024, Pages 18-36]
Fire
Fire simulation in the control room of Bushehr nuclear power plant by CFAST software [Volume 1, Issue 4, 2022-2023, Pages 10-14]
Fluent software
simulation of thermal conductivity and heat transfer of cermet fuel using Fluent software [Volume 1, Issue 3, 2022-2023, Pages 44-51]
Flux
Validation of deterministic and probabilistic methods for calculating kinetic parameters with experimental reactivity in new configuration of HWZPR reactor core [Volume 1, Issue 1, 2022-2023, Pages 9-23]
FMEA
Changes in core meltdown frequency due to implementation of RCM program on safety equipment of Bushehr nuclear power plant [Volume 2, Issue 1, 2023-2024, Pages 37-55]
Fortran
Investigation of Xenon concentration effect on the thermal conductivity of the gap between fuel and cladding in a PWR reactor [Volume 2, Issue 2, 2023-2024]
FRAPCON 3.1
Investigation of Xenon concentration effect on the thermal conductivity of the gap between fuel and cladding in a PWR reactor [Volume 2, Issue 2, 2023-2024]
FRAPCON code
Thermo-Mechanical Analysis of VVER-1000 Fuel Rods during Loss of Coolant Accident using FRAPTRAN code [Volume 1, Issue 1, 2022-2023, Pages 1-8]
FRAPTRAN code
Thermo-Mechanical Analysis of VVER-1000 Fuel Rods during Loss of Coolant Accident using FRAPTRAN code [Volume 1, Issue 1, 2022-2023, Pages 1-8]
FTA
Changes in core meltdown frequency due to implementation of RCM program on safety equipment of Bushehr nuclear power plant [Volume 2, Issue 1, 2023-2024, Pages 37-55]
Fuel rod
simulation of thermal conductivity and heat transfer of cermet fuel using Fluent software [Volume 1, Issue 3, 2022-2023, Pages 44-51]
Fuel rod performance
Thermo-Mechanical Analysis of VVER-1000 Fuel Rods during Loss of Coolant Accident using FRAPTRAN code [Volume 1, Issue 1, 2022-2023, Pages 1-8]
Fuel test loop
Evaluation of the Safety Systems of Tehran Research Reactor Fuel Test Loop during Loss of Flow Accident [Volume 1, Issue 4, 2022-2023, Pages 23-31]
Fusion neutron shielding
Biological Shield Design for Gamma and Neutron from 90 kJ Dense Plasma Focus [Volume 1, Issue 2, 2022-2023, Pages 39-46]
G
Gamma
Prediction of Air and Water Flow-Rates Independent of Flow Regimes Using Gamma-Ray Attenuation Technique and Artificial Neural Network [Volume 1, Issue 1, 2022-2023, Pages 49-54]
Gamma-ray attenuation
Feasibility study of 99Mo radioisotope production using uranium molten salt target irradiation by 30 Mev proton Cyclotron [Volume 1, Issue 1, 2022-2023, Pages 36-48]
Gaseous Diffusion system
Study of temperature effect of wall on gaseous diffusion separation using direct simulation Monte Carlo method (DSMC) [Volume 1, Issue 2, 2022-2023, Pages 53-63]
GEANT4
Biological Shield Design for Gamma and Neutron from 90 kJ Dense Plasma Focus [Volume 1, Issue 2, 2022-2023, Pages 39-46]
H
Heaving and Rolling
Numerical simulation of fluid flow due to sea waves in a Channel without heat transfer using FLUENT software [Volume 1, Issue 2, 2022-2023, Pages 13-26]
High-Pressure Test Facilities
Design, Simulation and Evaluation of Pressure Control System in a High-pressure Research Test loop [Volume 1, Issue 4, 2022-2023, Pages 1-9]
Human Error
Level 1 Probabilistic Safety Assessment at Zero Power Heavy Water Reactor (HWZPR) [(Articles in Press)]
HWZPR
Validation of deterministic and probabilistic methods for calculating kinetic parameters with experimental reactivity in new configuration of HWZPR reactor core [Volume 1, Issue 1, 2022-2023, Pages 9-23]
HWZPR
Level 1 Probabilistic Safety Assessment at Zero Power Heavy Water Reactor (HWZPR) [(Articles in Press)]
I
Integral of absolute error
Design of an optimized PID control system for Tehran research reactor based on TLBO algorithm [Volume 1, Issue 3, 2022-2023, Pages 1-13]
Ion Exchange Chromatography
The Alpha-Spectroscopy of U and Th Isotopes of the Saghand Ore Anomaly 2 and the Surface Part Anomaly 1 [Volume 1, Issue 3, 2022-2023, Pages 14-25]
Ion transmission probability
Quadrupole simulation in a mass spectrometer [Volume 1, Issue 2, 2022-2023, Pages 27-38]
Iterated Fission Probability
Validation of deterministic and probabilistic methods for calculating kinetic parameters with experimental reactivity in new configuration of HWZPR reactor core [Volume 1, Issue 1, 2022-2023, Pages 9-23]
L
Leaching
The Alpha-Spectroscopy of U and Th Isotopes of the Saghand Ore Anomaly 2 and the Surface Part Anomaly 1 [Volume 1, Issue 3, 2022-2023, Pages 14-25]
Leakage current
Evaluation of leakage current variations of silicon diode irradiated by reactor neutrons using molecular dynamic calculations [Volume 1, Issue 1, 2022-2023, Pages 24-35]
Linearized fractional neutron point kinetics
Design of an optimized PID control system for Tehran research reactor based on TLBO algorithm [Volume 1, Issue 3, 2022-2023, Pages 1-13]
Loss of coolant accident
Level 1 Probabilistic Safety Assessment at Zero Power Heavy Water Reactor (HWZPR) [(Articles in Press)]
Loss of flow accident
Evaluation of the Safety Systems of Tehran Research Reactor Fuel Test Loop during Loss of Flow Accident [Volume 1, Issue 4, 2022-2023, Pages 23-31]
M
Magnesium oxide
Thermoluminescence properties study of magnesium oxide doped with lanthanides and lithium under gamma irradiation for dosimetric applications [Volume 1, Issue 2, 2022-2023, Pages 1-12]
Main control room
Fire simulation in the control room of Bushehr nuclear power plant by CFAST software [Volume 1, Issue 4, 2022-2023, Pages 10-14]
Mann’s model
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, 2023-2024, Pages 56-64]
Mass source
Modeling and simulation of gas behavior with DSMC method and calculating the separation parameters inside a gas centrifuge [Volume 1, Issue 3, 2022-2023, Pages 26-35]
MCNP code
Validation of deterministic and probabilistic methods for calculating kinetic parameters with experimental reactivity in new configuration of HWZPR reactor core [Volume 1, Issue 1, 2022-2023, Pages 9-23]
MCNPX
Evaluation of leakage current variations of silicon diode irradiated by reactor neutrons using molecular dynamic calculations [Volume 1, Issue 1, 2022-2023, Pages 24-35]
MCNPX
Biological Shield Design for Gamma and Neutron from 90 kJ Dense Plasma Focus [Volume 1, Issue 2, 2022-2023, Pages 39-46]
MCNPX
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, 2023-2024, Pages 56-64]
MCNPX2.7.0
Investigation of reflector role in neutronic and control parameters of small modular reactor core using Monte Carlo modeling [Volume 2, Issue 1, 2023-2024, Pages 11-17]
Mixing coefficient
Simulation and Analysis of the Coolant Mixing Test within the Reactor Pressure Vessel of BNPP Using ANSYS CFX 18.0 [Volume 2, Issue 1, 2023-2024, Pages 1-10]
MNSR
Investigation of the dynamic behavior of the Isfahan miniature neutron source reactor core during the reactivity injection accident [Volume 2, Issue 2, 2023-2024]
Molecular and continuous region
Modeling and simulation of gas behavior with DSMC method and calculating the separation parameters inside a gas centrifuge [Volume 1, Issue 3, 2022-2023, Pages 26-35]
Molecular dynamic
Evaluation of leakage current variations of silicon diode irradiated by reactor neutrons using molecular dynamic calculations [Volume 1, Issue 1, 2022-2023, Pages 24-35]
Monte-carlo
Redesign of Tehran Research Reactor Core by using UO2 Plate Fuel [Volume 2, Issue 2, 2023-2024]
Monte Carlo dodes
Biological Shield Design for Gamma and Neutron from 90 kJ Dense Plasma Focus [Volume 1, Issue 2, 2022-2023, Pages 39-46]
MTR_PC package
Validation of deterministic and probabilistic methods for calculating kinetic parameters with experimental reactivity in new configuration of HWZPR reactor core [Volume 1, Issue 1, 2022-2023, Pages 9-23]
Multipoint Kinetic
Comparison of multipoint kinetic with methods of the direct solution of diffusion equation and conventional point kinetic for investigation of nuclear reactors transient [Volume 1, Issue 1, 2022-2023, Pages 58-68]
N
NaI(Tl)
Feasibility study of 99Mo radioisotope production using uranium molten salt target irradiation by 30 Mev proton Cyclotron [Volume 1, Issue 1, 2022-2023, Pages 36-48]
NaI(Tl) Detector
Prediction of Air and Water Flow-Rates Independent of Flow Regimes Using Gamma-Ray Attenuation Technique and Artificial Neural Network [Volume 1, Issue 1, 2022-2023, Pages 49-54]
Neutron Beam Energy
Measurement of Emitted Neutron and Deuteron Energies in a Dense Plasma Focus Device [Volume 2, Issue 2, 2023-2024]
Neutron Diffusion Equation
Solving Multigroup, One-dimensional Neutron Transport Equation Using SDP1 Method [Volume 2, Issue 1, 2023-2024, Pages 18-36]
Neutron flux
Investigation of reflector role in neutronic and control parameters of small modular reactor core using Monte Carlo modeling [Volume 2, Issue 1, 2023-2024, Pages 11-17]
Neutronic parameters
Simulation and investigation of neutronic parameters of Tehran research reactor core using probabilistic codes [(Articles in Press)]
Neutronic Simulation
Redesign of Tehran Research Reactor Core by using UO2 Plate Fuel [Volume 2, Issue 2, 2023-2024]
Neutron radiography
Introducing a polymeric setup with maximum thermal neutron removal for neutron radiographic shutter design [Volume 1, Issue 2, 2022-2023, Pages 47-52]
Neutron Shielding
Introducing a polymeric setup with maximum thermal neutron removal for neutron radiographic shutter design [Volume 1, Issue 2, 2022-2023, Pages 47-52]
Neutron Transport Equation
Solving Multigroup, One-dimensional Neutron Transport Equation Using SDP1 Method [Volume 2, Issue 1, 2023-2024, Pages 18-36]
Nuclear
Investigation of the dynamic behavior of the Isfahan miniature neutron source reactor core during the reactivity injection accident [Volume 2, Issue 2, 2023-2024]
Nuclear reactor
simulation of thermal conductivity and heat transfer of cermet fuel using Fluent software [Volume 1, Issue 3, 2022-2023, Pages 44-51]
Nuscale reactor
simulation of thermal conductivity and heat transfer of cermet fuel using Fluent software [Volume 1, Issue 3, 2022-2023, Pages 44-51]
O
Optimized PID controller
Design of an optimized PID control system for Tehran research reactor based on TLBO algorithm [Volume 1, Issue 3, 2022-2023, Pages 1-13]
P
Passive Heat Removal System (PHRS)
Thermo-Hydraulic Analysis of Passive Heat Removal System (PHRS) in VVER-1000 Nuclear Reactor Using RELAP5 Code [Volume 1, Issue 4, 2022-2023, Pages 32-42]
PID Controller
Design, Simulation and Evaluation of Pressure Control System in a High-pressure Research Test loop [Volume 1, Issue 4, 2022-2023, Pages 1-9]
Plasma Focus Device
Measurement of Emitted Neutron and Deuteron Energies in a Dense Plasma Focus Device [Volume 2, Issue 2, 2023-2024]
Polymeric composite
Introducing a polymeric setup with maximum thermal neutron removal for neutron radiographic shutter design [Volume 1, Issue 2, 2022-2023, Pages 47-52]
Porous membrane
Study of temperature effect of wall on gaseous diffusion separation using direct simulation Monte Carlo method (DSMC) [Volume 1, Issue 2, 2022-2023, Pages 53-63]
Power Peaking Factor
Investigation of Increasing Safety and Reliability of Small Modular Reactors Using Dual-cooled Annular Fuel Element [Volume 1, Issue 4, 2022-2023, Pages 15-22]
Pressurizer
Design, Simulation and Evaluation of Pressure Control System in a High-pressure Research Test loop [Volume 1, Issue 4, 2022-2023, Pages 1-9]
Probability codes
Simulation and investigation of neutronic parameters of Tehran research reactor core using probabilistic codes [(Articles in Press)]
PSA
Changes in core meltdown frequency due to implementation of RCM program on safety equipment of Bushehr nuclear power plant [Volume 2, Issue 1, 2023-2024, Pages 37-55]
PSA
Success Criteria Analysis of Steam Line Break for a Typical Two-loop Westinghouse PWR [Volume 2, Issue 2, 2023-2024]
PSA
Level 1 Probabilistic Safety Assessment at Zero Power Heavy Water Reactor (HWZPR) [(Articles in Press)]
Q
Quadrupole mass filter
Quadrupole simulation in a mass spectrometer [Volume 1, Issue 2, 2022-2023, Pages 27-38]
R
Radiation
The Alpha-Spectroscopy of U and Th Isotopes of the Saghand Ore Anomaly 2 and the Surface Part Anomaly 1 [Volume 1, Issue 3, 2022-2023, Pages 14-25]
Radiation model
A comprehensive review of radiation models in the space environment [Volume 2, Issue 2, 2023-2024]
Radioactive material dispersion
Assessment of Proposed Sites for the Establishment of Fars Research Reactor [Volume 2, Issue 1, 2023-2024, Pages 64-71]
Radioactive Minerals
The Alpha-Spectroscopy of U and Th Isotopes of the Saghand Ore Anomaly 2 and the Surface Part Anomaly 1 [Volume 1, Issue 3, 2022-2023, Pages 14-25]
RCM
Changes in core meltdown frequency due to implementation of RCM program on safety equipment of Bushehr nuclear power plant [Volume 2, Issue 1, 2023-2024, Pages 37-55]
Reactivity
Investigation of the dynamic behavior of the Isfahan miniature neutron source reactor core during the reactivity injection accident [Volume 2, Issue 2, 2023-2024]
Reactor Dynamic
Comparison of multipoint kinetic with methods of the direct solution of diffusion equation and conventional point kinetic for investigation of nuclear reactors transient [Volume 1, Issue 1, 2022-2023, Pages 58-68]
Reactor neutron spectrum
Evaluation of leakage current variations of silicon diode irradiated by reactor neutrons using molecular dynamic calculations [Volume 1, Issue 1, 2022-2023, Pages 24-35]
Reactor pressure vessel
Simulation and Analysis of the Coolant Mixing Test within the Reactor Pressure Vessel of BNPP Using ANSYS CFX 18.0 [Volume 2, Issue 1, 2023-2024, Pages 1-10]
RELAP5 code
Thermo-Hydraulic Analysis of Passive Heat Removal System (PHRS) in VVER-1000 Nuclear Reactor Using RELAP5 Code [Volume 1, Issue 4, 2022-2023, Pages 32-42]
Reliability
Changes in core meltdown frequency due to implementation of RCM program on safety equipment of Bushehr nuclear power plant [Volume 2, Issue 1, 2023-2024, Pages 37-55]
Repair and maintenance
Changes in core meltdown frequency due to implementation of RCM program on safety equipment of Bushehr nuclear power plant [Volume 2, Issue 1, 2023-2024, Pages 37-55]
Research reactor
Assessment of Proposed Sites for the Establishment of Fars Research Reactor [Volume 2, Issue 1, 2023-2024, Pages 64-71]
S
Safety evaluation
Evaluation of the Safety Systems of Tehran Research Reactor Fuel Test Loop during Loss of Flow Accident [Volume 1, Issue 4, 2022-2023, Pages 23-31]
Saghand
The Alpha-Spectroscopy of U and Th Isotopes of the Saghand Ore Anomaly 2 and the Surface Part Anomaly 1 [Volume 1, Issue 3, 2022-2023, Pages 14-25]
Sawada method
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, 2022-2023, Pages 52-64]
Shutter
Introducing a polymeric setup with maximum thermal neutron removal for neutron radiographic shutter design [Volume 1, Issue 2, 2022-2023, Pages 47-52]
Sickafus method
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, 2022-2023, Pages 52-64]
Silicon diode
Evaluation of leakage current variations of silicon diode irradiated by reactor neutrons using molecular dynamic calculations [Volume 1, Issue 1, 2022-2023, Pages 24-35]
SILVACO
Evaluation of leakage current variations of silicon diode irradiated by reactor neutrons using molecular dynamic calculations [Volume 1, Issue 1, 2022-2023, Pages 24-35]
Simulink
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, 2023-2024, Pages 56-64]
Site evaluation process
Assessment of Proposed Sites for the Establishment of Fars Research Reactor [Volume 2, Issue 1, 2023-2024, Pages 64-71]
Site Selection
Assessment of Proposed Sites for the Establishment of Fars Research Reactor [Volume 2, Issue 1, 2023-2024, Pages 64-71]
Small modular reactor
Investigation of Increasing Safety and Reliability of Small Modular Reactors Using Dual-cooled Annular Fuel Element [Volume 1, Issue 4, 2022-2023, Pages 15-22]
Small modular reactor
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, 2023-2024, Pages 56-64]
Small modular reactor
Conceptual Design and reactivity control of long-life and LEU soluble boron free
Hexagonal Fuel Assembly [Volume 1, Issue 4, 2022-2023, Pages 43-52]
Small Modular Reactor (SMR)
Investigation of reflector role in neutronic and control parameters of small modular reactor core using Monte Carlo modeling [Volume 2, Issue 1, 2023-2024, Pages 11-17]
SMR
Numerical simulation of fluid flow due to sea waves in a Channel without heat transfer using FLUENT software [Volume 1, Issue 2, 2022-2023, Pages 13-26]
Solar events
A comprehensive review of radiation models in the space environment [Volume 2, Issue 2, 2023-2024]
Space environment
A comprehensive review of radiation models in the space environment [Volume 2, Issue 2, 2023-2024]
Success Criteria Analysis؛ MSLB
Success Criteria Analysis of Steam Line Break for a Typical Two-loop Westinghouse PWR [Volume 2, Issue 2, 2023-2024]
T
Tehran reactor core
Redesign of Tehran Research Reactor Core by using UO2 Plate Fuel [Volume 2, Issue 2, 2023-2024]
Tehran reactor core
Simulation and investigation of neutronic parameters of Tehran research reactor core using probabilistic codes [(Articles in Press)]
Tehran research reactor
Design of an optimized PID control system for Tehran research reactor based on TLBO algorithm [Volume 1, Issue 3, 2022-2023, Pages 1-13]
Tehran research reactor
Evaluation of the Safety Systems of Tehran Research Reactor Fuel Test Loop during Loss of Flow Accident [Volume 1, Issue 4, 2022-2023, Pages 23-31]
Thermal Conductivity
Investigation of Xenon concentration effect on the thermal conductivity of the gap between fuel and cladding in a PWR reactor [Volume 2, Issue 2, 2023-2024]
Thermal-hydraulic Analysis
Redesign of Tehran Research Reactor Core by using UO2 Plate Fuel [Volume 2, Issue 2, 2023-2024]
Thermoluminescence
Thermoluminescence properties study of magnesium oxide doped with lanthanides and lithium under gamma irradiation for dosimetric applications [Volume 1, Issue 2, 2022-2023, Pages 1-12]
Thorium
The Alpha-Spectroscopy of U and Th Isotopes of the Saghand Ore Anomaly 2 and the Surface Part Anomaly 1 [Volume 1, Issue 3, 2022-2023, Pages 14-25]
TLBO algorithm
Design of an optimized PID control system for Tehran research reactor based on TLBO algorithm [Volume 1, Issue 3, 2022-2023, Pages 1-13]
Transient state
Comparison of multipoint kinetic with methods of the direct solution of diffusion equation and conventional point kinetic for investigation of nuclear reactors transient [Volume 1, Issue 1, 2022-2023, Pages 58-68]
Trapped particles
A comprehensive review of radiation models in the space environment [Volume 2, Issue 2, 2023-2024]
Two
Prediction of Air and Water Flow-Rates Independent of Flow Regimes Using Gamma-Ray Attenuation Technique and Artificial Neural Network [Volume 1, Issue 1, 2022-2023, Pages 49-54]
Two-phase flow
Feasibility study of 99Mo radioisotope production using uranium molten salt target irradiation by 30 Mev proton Cyclotron [Volume 1, Issue 1, 2022-2023, Pages 36-48]
U
Uranium
The Alpha-Spectroscopy of U and Th Isotopes of the Saghand Ore Anomaly 2 and the Surface Part Anomaly 1 [Volume 1, Issue 3, 2022-2023, Pages 14-25]
V
VVER-1000 reactor
Thermo-Hydraulic Analysis of Passive Heat Removal System (PHRS) in VVER-1000 Nuclear Reactor Using RELAP5 Code [Volume 1, Issue 4, 2022-2023, Pages 32-42]
X
Xenon build-up - Monte Carlo Method
Simulating and analysis of neutronic parameters of a Soluble-Boron-Free
marine baise reactor core [(Articles in Press)]