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The denatured molten-salt reactor (DMSR) was an Oak Ridge theoretical design that was never built. Engel et al. 1980 said the project "examined the conceptual feasibility of a molten-salt power reactor fueled with denatured uranium-235 (i.e. with low-enriched uranium) and operated with a minimum of chemical processing."
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 ]
Passive decay heat cooling. Many reactor designs (such as that of the Molten-Salt Reactor Experiment) allow the fuel/coolant mixture to escape to a drain tank, when the reactor is not running (see "Fail safe core" below). This tank is planned to have some kind (details are still open) of passive decay heat removal, thus relying on physical ...
A sample of thorium. Thorium-based nuclear power generation is fueled primarily by the nuclear fission of the isotope uranium-233 produced from the fertile element thorium.A thorium fuel cycle can offer several potential advantages over a uranium fuel cycle [Note 1] —including the much greater abundance of thorium found on Earth, superior physical and nuclear fuel properties, and reduced ...
The IMSR belongs to the denatured molten salt reactor (DMSR) [7] class of molten salt reactors (MSR). It is designed to have all the safety features associated with the Molten Salt class of reactors including low pressure operation (the reactor and primary coolant is operated near normal atmospheric pressure), the inability to lose primary ...
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 relative lack of water available for cooling pressurized water reactors west of the Hu line (shaded yellow) is seen as a limiting factor for them. cf. Map of Chinese nuclear power plants A small modular reactor (SMR) based on the LF1, as well as a fuel salt research facility, is planned for the same site.
The nitrate salt is KNO 3-NaNO 2-NaNO 3 (44-49-7 mole %). A supercritical steam Rankine cycle is the selected power cycle. The water has a temperature of 1050°F(838.71 K) when it leaves the secondary heat exchanger, and it has a pressure of 3500 psa (24132 kPa).