Items related to Molten-Salt Reactor Experiment: Molten salt reactor,...
Molten-Salt Reactor Experiment: Molten salt reactor, Oak Ridge National Laboratory, Inherent safety, Hydrothermal circulation, Thorium, Breeder ... Uranium-233, Pyrolytic carbon, Hastelloy - Softcover
Présentation de l'éditeur
Please note that the content of this book primarily consists of articles available from Wikipedia or other free sources online. 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.
"About this title" may belong to another edition of this title.
- PublisherAlphascript Publishing
- Publication date2009
- ISBN 10 6130253176
- ISBN 13 9786130253172
- BindingBroché
- LanguageEnglish
- Number of pages96
- EditorMiller Frederic P., Vandome Agnes F., McBrewster John
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