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Molten-Salt Reactor Experiment
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High Quality Content by WIKIPEDIA articles! The Molten-Salt Reactor Experiment (MSRE) was an experimental molten-salt reactor at the Oak Ridge National Laboratory (ORNL); researching this technology through the 1960s. The MSRE was a 7.4 MWth test reactor simulating the neutronic "kernel" of an inherently safe epithermal thorium breeder reactor. It used three fuels: plutonium-239, uranium-235 and uranium-233. The last, 233UF4 was the result of breeding from thorium. Since this was an engineering test, the large, expensive breeding blanket of thorium salt was omitted in favor of neutron measurements. In the MSRE, the heat from the 650 °C core was shed via a cooling system using air blowers and radiators. It is thought similar reactors could power high-efficiency heat engines such as gas turbines. The MSRE was located at ORNL. Its piping, core vat and structural components were made from Hastelloy-N and its moderator was a pyrolytic graphite core. It went critical in 1965 and ran for four years.
Weitere Informationen
- Allgemeine Informationen
- GTIN 09786130253172
- Editor Frederic P. Miller, Agnes F. Vandome, John McBrewster
- Sprache Englisch
- Genre Physik & Astronomie
- Größe H5mm x B220mm x T150mm
- Jahr 2009
- EAN 9786130253172
- Format Kartonierter Einband
- ISBN 978-613-0-25317-2
- Titel Molten-Salt Reactor Experiment
- Untertitel Molten salt reactor, Oak Ridge National Laboratory, Inherent safety, Hydrothermal circulation, Thorium, Breeder reactor, Plutonium-239, Uranium-235, Uranium-233, Pyrolytic carbon, Hastelloy
- Gewicht 140g
- Herausgeber Alphascript Publishing
- Anzahl Seiten 96
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