Neutronic and fuel cycle performance analysis of fluoride and chloride fuels in Molten Salt Fast Reactor (MSFR)
Mahdi Aghili Nasr, A. Zolfaghari, Reza Akbari, Antonio Cammi, Shervineh Amirkhosravi
Topics & Concepts
Fissile materialNuclear engineeringMolten salt reactorBurnupDelayed neutronNeutron transportMolten saltEnvironmental scienceMaterials scienceNeutronNuclear physicsFissionPhysicsEngineeringMetallurgyNuclear reactor physics and engineeringGraphite, nuclear technology, radiation studiesNuclear Materials and Properties