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			<gallery>
			File:MSRE_Diagram.png\|Diagram of the Molten-Salt Reactor Experiment
			File:MoltenSaltReactor.jpg\|Molten Salt Reactor
			File:MSRE_Core.JPG\|Core of the Molten-Salt Reactor Experiment
			File:FLiBe.png\|FLiBe salt used in the reactor
			File:MSRE_Heat_Exchanger.JPG\|Heat exchanger of the Molten-Salt Reactor Experiment
			File:ARE_Building.JPG\|Aircraft Reactor Experiment building
			File:ORNL_Alvin_Weinberg_MSRE_6Kh.jpg\|Alvin Weinberg at the Molten-Salt Reactor Experiment
			File:MSRE_U-233_Seaborg_(14480987473).jpg\|Glenn Seaborg with U-233 at the Molten-Salt Reactor Experiment
			</gallery>

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'''Molten-Salt Reactor Experiment'''

The '''Molten-Salt Reactor Experiment''' ([[MSRE]]) was an experimental [[nuclear reactor]] which was operated from 1965 to 1969 by the [[Oak Ridge National Laboratory]] (ORNL) in the United States. The MSRE was a 7.4 MWth test reactor simulating the neutronic "kernel" of a type of inherently safer epithermal thorium molten salt breeder reactor.

==Design and Operation==

The MSRE was a [[thermal reactor]] that used a [[molten salt]] mixture of lithium, beryllium, and zirconium fluorides as both its [[reactor coolant]] and [[nuclear fuel]]. The fuel was a mixture of uranium-233 and uranium-235, both of which are [[fissile material]]s. The reactor was moderated by [[graphite]].

The MSRE was unique in that it had a liquid fuel, rather than solid fuel rods. This allowed for a much higher operating temperature and a much lower pressure than in a typical [[pressurized water reactor]] (PWR), which improved the efficiency of the power cycle.

==Results and Legacy==

The MSRE was successful in demonstrating the feasibility of molten salt reactors (MSRs) and in developing the technology needed for their operation. The experiment ended in 1969, but the data and experience gained continue to be used in studies of potential new MSRs.

The MSRE was also significant in that it was the first reactor to use [[uranium-233]] as a fuel, a product of [[thorium]] irradiation. This demonstrated the feasibility of the [[thorium fuel cycle]], which is seen as a potential way to produce nuclear power with less production of long-lived [[nuclear waste]].

==See also==
* [[Liquid fluoride thorium reactor]]
* [[Generation IV reactor]]
* [[Nuclear power in the United States]]

==References==
<references />

{{Nuclear technology}}
{{Energy technology}}
{{US DOE National Laboratories}}

[[Category:Nuclear reactors]]
[[Category:Nuclear technology]]
[[Category:Oak Ridge National Laboratory]]
[[Category:Energy technology]]
[[Category:Experimental reactors]]
[[Category:1965 establishments in the United States]]
[[Category:1969 disestablishments in the United States]]

{{nuclear-stub}}

Molten-Salt Reactor Experiment - Revision history

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