Iranian Journal of Physics Research

Neutronic and thermohydraulic analysis of annular fuels in MCNPX and ANSYS FLUENT for use in BNPP

Volume 24, Issue 4, Winter 2025, Pages 355-374

https://doi.org/10.47176/ijpr.24.4.61908

Zeinab Tayyari-Sadegh, Farhad Zolfagharpur

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Monte Carlo simulation of response function of organic scintillators to gamma rays and neutrons using FLUKA, MCNPX and SCINFUL code

Volume 17, Issue 5, Winter 2018, Pages 635-645

https://doi.org/10.29252/ijpr.17.5.635

M tajik, H Yousefnia

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Investigation of Isfahan miniature neutron source reactor (MNSR) for boron neutron capture therapy by MCNP simulation

Volume 14, Issue 4, Winter 2015, Pages 327-339

S.Z Kalantari, H Tavakoli, M Nami

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