affiliation not provided to SSRN
SD-TMSR, neutronic parameter, startup fuel, MCNP6.2
molten salt reactor, heavy water moderator, natural uranium, MCNP6.2, ENDF/B-VII.0
molten salt reactor, graphite density, neutronic parameter, fuel economy, MCNP
PCMSR, molten salt reactor, thorium, parametric analysis, MCNP6.2