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Nuclear and Hydro Power
Published in Anco S. Blazev, Energy Security for The 21st Century, 2021
Molten salts nuclear fuels have nuclear fuel dissolved directly in the molten salt coolant. Molten salt-fueled reactors, such as the liquid fluoride thorium reactor (LFTR), are different than molten salt-cooled reactors that do not dissolve nuclear fuel in the coolant.
The Other Energy Markets
Published in Anco S. Blazev, Global Energy Market Trends, 2021
Molten salts nuclear fuels have nuclear fuel dissolved directly in the molten salt coolant. Molten salt-fueled reactors, such as the liquid fluoride thorium reactor (LFTR), are different than molten salt-cooled reactors that do not dissolve nuclear fuel in the coolant. Molten salt fuels were used in the LFTR known as the Molten Salt Reactor Experiment, as well as other liquid core reactor experiments.
The Other Energy Sources
Published in Anco S. Blazev, Power Generation and the Environment, 2021
Molten salts nuclear fuels have nuclear fuel dissolved directly in the molten salt coolant. Molten salt-fueled reactors, such as the liquid fluoride thorium reactor (LFTR), are different than molten salt-cooled reactors that do not dissolve nuclear fuel in the coolant.
Safe, clean, proliferation resistant and cost-effective Thorium-based Molten Salt Reactors for sustainable development
Published in International Journal of Sustainable Energy, 2022
The more advanced reactor is the Molten Salt Breeder (MSBR), also started at ORNL, and described in detail by (Robertson et al. 1970). This is a breeder reactor, implying that more fissile material is created than consumed in the fission process, and it consists of two fluids. A representative design is the Liquid Fluoride Thorium Reactor (LFTR). The LFTR consists of a core and a ‘blanket,’ a volume that surrounds the core. The blanket contains a mixture of thorium tetrafluoride in a fluoride salt containing lithium and beryllium, made molten by the heat of the core. The core consists of fissile uranium-233 tetrafluoride also in molten fluoride salts of lithium and beryllium within a graphite structure that serves as a moderator and neutron reflector. The uranium-233 is produced in the blanket when neutrons generated in the core are absorbed (Hargraves and Moir 2010).