Investigation of 99Mo potential production via UO2SO4 liquid target irradiation in a 5 MW nuclear research reactor
Gholamzadeh, Zohreh, Mirvakili, Seyed Mohammad, Davari, Amin, Alizadeh, Mosoumeh, Joz-Vaziri, Atieh
Burn-up calculation of different thorium-based fuel matrixes in a thermal research reactor using MCNPX 2.6 code
Gholamzadeh, Zohreh, Hossein Feghhi, Seyed Amir, Soltani, Leila, Rezazadeh, Marzieh, Tenreiro, Claudio, Joharifard, Mahdi