Keywords and Phrases
Thorium Molten Salt Reactor (TMSR)
"The Generation IV International Forum placed six reactors as priority for research and development to compensate for the world's increasing energy demands. Among the six were Molten Salt Reactors (MSRs). These reactors utilize the Th/233U fuel cycle using molten fluoride or chloride salts as coolants. MSRs also have the possibility to use other fissile fuels especially with the first fleet of reactors given the low amount of Uranium-233 available commercially.
With the possibility of diverting from using 233U initially, the research presented here will benchmark 233U as a main fuel for MSRs using the Thorium Molten Salt Reactor (TMSR) designed by Billebaud Annick and her team at the Laboratory for Subatomic Particles and Cosmology in France. Uranium-235 and Plutonium-239 will then be tested as suitable initial fuels for the first fleet of TMSRs. These fuels will be compared to the reference data based on neutron flux spectra and breeding capabilities."--Abstract, page iii.
Alajo, Ayodeji Babatunde
Mueller, Gary Edward, 1954-
Nuclear Engineering and Radiation Science
M.S. in Nuclear Engineering
Missouri University of Science and Technology
vii, 48 pages
© 2015 Dustin Gage Green, All rights reserved.
Thesis - Open Access
Molten Salt Reactors
Neutron flux -- Measurement
Electronic OCLC #
Link to Catalog Record
Green, Dustin Gage, "Initial fuel possibilities for the Thorium Molten Salt Reactor" (2015). Masters Theses. 7398.