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]
C
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]
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]
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]
Cosmic rays
A comprehensive review of radiation models in the space environment [Volume 2, Issue 2, 2023-2024]
D
D-D Fusion Reactions
Measurement of Emitted Neutron and Deuteron Energies in a Dense Plasma Focus Device [Volume 2, Issue 2, 2023-2024]
Deterministic Safety Analysis
Success Criteria Analysis of Steam Line Break for a Typical Two-loop Westinghouse PWR [Volume 2, Issue 2, 2023-2024]
Deuterium Beam Energy
Measurement of Emitted Neutron and Deuteron Energies in a Dense Plasma Focus Device [Volume 2, Issue 2, 2023-2024]
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]
Double-Spherical Harmonics Method
Solving Multigroup, One-dimensional Neutron Transport Equation Using SDP1 Method [Volume 2, Issue 1, 2023-2024, Pages 18-36]
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
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]
F
Finite Element Method
Solving Multigroup, One-dimensional Neutron Transport Equation Using SDP1 Method [Volume 2, Issue 1, 2023-2024, Pages 18-36]
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]
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]
M
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]
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]
Monte-carlo
Redesign of Tehran Research Reactor Core by using UO2 Plate Fuel [Volume 2, Issue 2, 2023-2024]
N
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 Simulation
Redesign of Tehran Research Reactor Core by using UO2 Plate Fuel [Volume 2, Issue 2, 2023-2024]
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]
P
Plasma Focus Device
Measurement of Emitted Neutron and Deuteron Energies in a Dense Plasma Focus Device [Volume 2, Issue 2, 2023-2024]
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]
R
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]
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 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]
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
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
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 (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]
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]
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]
Trapped particles
A comprehensive review of radiation models in the space environment [Volume 2, Issue 2, 2023-2024]