Year
2013
Abstract
. Molten salt reactors (MSRs) are often advocated as a radi- cal but worthwhile alternative to traditional reactor concepts based on solid fuels. This article builds upon the existing research into MSRs, most of it carried out at Oak Ridge National Laboratory until government-sponsored research was canceled in the 1970s, to model and simulate the operation of various types of MSRs using the MCNP Monte Carlo neutron transport code. Types of MSRs considered include pure thorium-fueled single- uid and two- uid breeder reactors, a denatured thorium-fueled reactor, and a low-enriched uranium-fueled reactor. The paper analyzes specically the resource utilization and proliferation-risk attributes compared to those of standard light-water reactors and assesses the viability of proposed designs for large-scale deployment.