Volume 2 (2023-2024)
Volume 1 (2022-2023)
Number of Articles: 6
Simulation and Analysis of the Coolant Mixing Test within the Reactor Pressure Vessel of BNPP Using ANSYS CFX 18.0
Pages 1-10
Investigation of reflector role in neutronic and control parameters of small modular reactor core using Monte Carlo modeling
Pages 11-17
Solving Multigroup, One-dimensional Neutron Transport Equation Using SDP1 Method
Pages 18-36
Changes in core meltdown frequency due to implementation of RCM program on safety equipment of Bushehr nuclear power plant
Pages 37-55
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
Pages 56-64
Assessment of Proposed Sites for the Establishment of Fars Research Reactor
Pages 64-71