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The Molten-Salt Reactor Experiment (MSRE) was an experimental molten-salt reactor research reactor at the Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee. This technology was researched through the 1960s, the reactor was constructed by 1964, it went critical in 1965, and was operated until 1969. [ 1 ]
Example of a molten-salt reactor scheme. A molten-salt reactor (MSR) is a class of nuclear fission reactor in which the primary nuclear reactor coolant and/or the fuel is a mixture of molten salt with a fissile material. Two research MSRs operated in the United States in the mid-20th century.
Due to the success of both the Aircraft Reactor Experiment (ARE) and Molten Salt Reactor Experiment (MSRE), ORNL went on to design a MSDR and a Molten Salt Breeder Reactor (MSBR). The MSDR is a 750 MW th MSR design that uses LiF-BeF 2-ThF 4-UF 4 (71.5-16.0-12.0-0.5 mole %) as the primary fuel salt.
The core of the Molten Salt Reactor Experiment. In 1950 the Oak Ridge School of Reactor Technology was established with two courses in reactor operation and safety; almost 1,000 students graduated. [22] Much of the research performed at ORNL in the 1950s was related to nuclear reactors as a form of energy production, both for propulsion and ...
The Molten-Salt Reactor Experiment [14] (MSRE) was a molten salt reactor run by the Oak Ridge National Laboratory. It was nuclear graphite moderated and the coolant salt used was FLiBe, which also carried the uranium-233 fluoride fuel dissolved in it. The MSRE had a negative temperature coefficient of reactivity: as the FLiBe temperature ...
The U.S. Nuclear Regulatory Commission is issuing a construction permit for a new type of nuclear reactor that uses molten salt to cool the reactor core. The NRC is issuing the permit to Kairos ...
The Molten-Salt Reactor Experiment (MSRE) set a record for continuous operation and was the first to use Thorium irradiated to produce uranium-233 as fuel. It also used plutonium-239 and the standard, naturally occurring uranium-235 .
Molten salt fuels were used in the LFTR known as the Molten Salt Reactor Experiment, as well as other liquid core reactor experiments. The liquid fuel for the molten salt reactor was a mixture of lithium, beryllium, thorium and uranium fluorides: LiF-BeF 2-ThF 4-UF 4 (72-16-12-0.4 mol%). It had a peak operating temperature of 705 °C in the ...