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Enhanced fuel production in thorium fusion hybrid blankets utilizing uranium multipliers [electronic resource]

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Bibliographic Details
Online Access: Online Access
Corporate Author: Pennsylvania State University (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Oak Ridge, Tenn. : distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1979.
Subjects:
Hybrid Reactors.
Alkali Metals.
Thorium Compounds.
Breeding Blankets.
Shielding.
Metals.
Uranium Compounds.
Thorium Cycle.
Uranium Oxides.
Lithium Compounds.
Oxygen Compounds.
Fuel Cycle.
Actinide Compounds.
Alkali Metal Compounds.
Lithium Oxides.
Reactor Components.
Oxides.
Elements.
Thorium Oxides.
Lithium.
Chalcogenides.
Plasma Physics And Fusion Technology.
Description
Abstract:The multiplication of 14 MeV D-T fusion neutrons via (n,2n), (n,3n), and fission reactions by ²³⁸U is well known and established. This study consistently evaluates the effectiveness of a depleted (tails) UO₂ multiplier on increasing the production of ²³³U and tritium in a thorium/lithium fusion--fission hybrid blanket. Nuclear performance is evaluated as a function of exposure and zone thickness.
Item Description:Published through SciTech Connect.
01/25/1979.
"wfps-tme-79-008"
" conf-790602-33"
ANS annual meeting, Atlanta, GA, USA, 3 Jun 1979.
Chapin, D.L.; Pitulski, R.H.; Klevans, E.
Westinghouse Electric Corp., Pittsburgh, PA (USA). Fusion Power Systems Dept.
Physical Description:Pages: 6 : digital, PDF file.

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