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Much of their work culminated with the Molten-Salt Reactor Experiment (MSRE). MSRE was a 7.4 MW th test reactor simulating the neutronic "kernel" of a type of epithermal thorium molten salt breeder reactor called the liquid fluoride thorium reactor (LFTR). The large (expensive) breeding blanket of thorium salt was omitted in favor of neutron ...
The reactor will utilise a reactor pressure vessel made of 20MnMoNi55 steel [7] also known as “APURVA” (Advanced Purified Reactor Vessel Alloy). [4] BARC disclosed in January 2020 that a Core catcher design has been validated that can manage a 100% core melt accident.
MoltexFLEX is a British nuclear energy company developing small modular molten salt reactors.Their reactor designs, termed "FLEX reactors", are stable salt reactors, and feature a hybrid approach whereby fuel assemblies similar to current light water reactors containing the liquid salt fuel mixture are submerged in a pool of liquid salt coolant.
Printable version; In other projects Wikidata item; Appearance. move to sidebar hide. Help Pages in category "Molten salt reactors" ... Pages in category "Molten salt ...
The reactor is proprietary molten salt reactor design that builds on two existing designs: the Denatured Molten Salt Reactor (DMSR) and Small Modular Advanced High Temperature Reactor (smAHRT). Both designs are from Oak Ridge National Laboratory. The key technology of the IMSR® is the integration of the primary reactor components, the ...
Th-232/U-233 is best suited to molten salt reactors (MSR). [12] Alvin M. Weinberg pioneered the use of the MSR at Oak Ridge National Laboratory. At ORNL, two prototype molten salt reactors were successfully designed, constructed and operated. These were the Aircraft Reactor Experiment in 1954 and Molten-Salt Reactor Experiment from 1965 to 1969 ...
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 ...
Molten-salt reactors are a type of nuclear reactor that uses molten salt(s) as a coolant or as a solvent in which the fissile material is dissolved. Experimental salts using lithium can be formed that have a melting point of 116 °C while still having a heat capacity of 1.54 J/(g·K). [4]