Quality of fissile fuel bred in a fusion reactor blanket

Quality of fissile fuel bred in a fusion reactor blanket [electronic resource]

Neutronic calculations were made of a hybrid CTR blanket consisting of uranium and thorium fuel. The calculational model is described. Transmutation calculations for the UO/sub 2/ blanket were performed for a number of irradiation times ranging from 100 to 1200 days. The mass of each isotope generat...

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Bibliographic Details
Online Access: Online Access
Corporate Author: Battelle Memorial Institute (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Columbus, Ohio : Oak Ridge, Tenn. : Battelle Memorial Institute ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy, 1976.
Subjects:
Breeding Blankets.
Breeding.
Neptunium 237.
Nuclear Fuels.
Plutonium 236.
Plutonium 238.
Plutonium 239.
Plutonium 240.
Plutonium 241.
Plutonium 242.
Protactinium 231.
Protactinium 233.
Uranium 232.
Uranium 233.
Uranium 234.
Hybrid Reactors.
Performance.
Actinide Isotopes.
Actinide Nuclei.
Alpha Decay Radioisotopes.
Beta Decay Radioisotopes.
Beta-Minus Decay Radioisotopes.
Days Living Radioisotopes.
Energy Sources.
Even-Even Nuclei.
Even-Odd Nuclei.
Fuels.
Heavy Nuclei.
Isotopes.
Neptunium Isotopes.
Nuclear Fuel Conversion.
Nuclei.
Odd-Even Nuclei.
Plutonium Isotopes.
Protactinium Isotopes.
Radioisotopes.
Reactor Components.
Reactor Materials.
Uranium Isotopes.
Years Living Radioisotopes.
Plasma Physics And Fusion Technology.

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Call Number: E 1.99: conf-760935-19
E 1.99: conf-760935-19 Available

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