Nuclear Technology and Energy

Simulation and Analysis of the Coolant Mixing Test within the Reactor Pressure Vessel of BNPP Using ANSYS CFX 18.0

Pages 1-10

https://doi.org/10.48308/nucte.2023.102645

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Investigation of reflector role in neutronic and control parameters of small modular reactor core using Monte Carlo modeling

Pages 11-17

https://doi.org/10.48308/nucte.2023.102646

mohammadreza Nematollahi

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Solving Multigroup, One-dimensional Neutron Transport Equation Using SDP1 Method

Pages 18-36

https://doi.org/10.48308/nucte.2023.102649

Masoud Nazari

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Changes in core meltdown frequency due to implementation of RCM program on safety equipment of Bushehr nuclear power plant

Pages 37-55

https://doi.org/10.48308/nucte.2023.102650

ali varchandi, mohammadreza abbasi

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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

https://doi.org/10.48308/nucte.2023.102651

Amir Sadegh Noe doost

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Assessment of Proposed Sites for the Establishment of Fars Research Reactor

Pages 64-71

https://doi.org/10.48308/nucte.2023.103497

Ebrahim Ghanbari

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