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Enhanced fuel production in thorium fusion hybrid blankets utilizing uranium multipliers

Conference ·
OSTI ID:6227050
; ;
The multiplication of 14 MeV D-T fusion neutrons via (n,2n), (n,3n), and fission reactions by /sup 238/U is well known and established. This study consistently evaluates the effectiveness of a depleted (tails) UO/sub 2/ multiplier on increasing the production of /sup 233/U and tritium in a thorium/lithium fusion--fission hybrid blanket. Nuclear performance is evaluated as a function of exposure and zone thickness.
Research Organization:
Westinghouse Electric Corp., Pittsburgh, PA (USA). Fusion Power Systems Dept.; Pennsylvania State Univ., University Park (USA)
DOE Contract Number:
EG-77-C-02-4544
OSTI ID:
6227050
Report Number(s):
WFPS-TME-79-008; CONF-790602-33
Country of Publication:
United States
Language:
English

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Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700205* -- Fusion Power Plant Technology-- Fuel
Heating
& Injection Systems
ACTINIDE COMPOUNDS
ALKALI METAL COMPOUNDS
ALKALI METALS
BREEDING BLANKETS
CHALCOGENIDES
ELEMENTS
FUEL CYCLE
HYBRID REACTORS
LITHIUM
LITHIUM COMPOUNDS
LITHIUM OXIDES
METALS
OXIDES
OXYGEN COMPOUNDS
REACTOR COMPONENTS
SHIELDING
THORIUM COMPOUNDS
THORIUM CYCLE
THORIUM OXIDES
URANIUM COMPOUNDS
URANIUM OXIDES