Fission-suppressed blankets for fissile fuel breeding fusion reactors
Journal Article
·
· J. Fusion Energy; (United States)
Two blanket concepts for deuterium-tritium (DT) fusion reactors are presented which maximize fissile fuel production while at the same time suppress fission reactions. By suppressing fission reactions, the reactor will be less hazardous, and thereforeeasier to design, develop, and license. A fusion breeder operating a given nuclear power level canproduce much more fissile fuel by suppressing fission reactions. The two blankets described use beryllium for neutron multiplication. One blanket uses two separate circulating molten salts: one salt for tritium breeding and the other salt for U-233 breeding. The other uses separate solid forms of lithium and thorium for breeding and helium for cooling.
- Research Organization:
- Lawrence Livermore National Lab., Univ. of California, Berkeley, CA
- OSTI ID:
- 5136749
- Journal Information:
- J. Fusion Energy; (United States), Journal Name: J. Fusion Energy; (United States) Vol. 1:3; ISSN JFEND
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
700205 -- Fusion Power Plant Technology-- Fuel
Heating
& Injection Systems
ACTINIDE COMPOUNDS
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALKALI METAL COMPOUNDS
ALKALINE EARTH METAL COMPOUNDS
ALPHA DECAY RADIOISOTOPES
BERYLLIUM COMPOUNDS
BERYLLIUM FLUORIDES
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDING
BREEDING BLANKETS
BREEDING RATIO
CONVERSION RATIO
COST BENEFIT ANALYSIS
D-T REACTORS
EVEN-ODD NUCLEI
FEASIBILITY STUDIES
FISSILE MATERIALS
FISSION
FISSIONABLE MATERIALS
FLUORIDES
FLUORINE COMPOUNDS
HALIDES
HALOGEN COMPOUNDS
HEAVY NUCLEI
HYBRID REACTORS
HYDROGEN ISOTOPES
INHIBITION
ISOTOPES
LIGHT NUCLEI
LITHIUM COMPOUNDS
LITHIUM FLUORIDES
LITHIUM HALIDES
MATERIALS
MOLTEN SALTS
NUCLEAR FUEL CONVERSION
NUCLEAR REACTION YIELD
NUCLEAR REACTIONS
NUCLEI
ODD-EVEN NUCLEI
RADIOISOTOPES
REACTOR COMPONENTS
SALTS
THERMONUCLEAR REACTOR MATERIALS
THERMONUCLEAR REACTORS
THORIUM COMPOUNDS
THORIUM FLUORIDES
TRITIUM
URANIUM 233
URANIUM ISOTOPES
YEARS LIVING RADIOISOTOPES
YIELDS
700201* -- Fusion Power Plant Technology-- Blanket Engineering
700205 -- Fusion Power Plant Technology-- Fuel
Heating
& Injection Systems
ACTINIDE COMPOUNDS
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALKALI METAL COMPOUNDS
ALKALINE EARTH METAL COMPOUNDS
ALPHA DECAY RADIOISOTOPES
BERYLLIUM COMPOUNDS
BERYLLIUM FLUORIDES
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDING
BREEDING BLANKETS
BREEDING RATIO
CONVERSION RATIO
COST BENEFIT ANALYSIS
D-T REACTORS
EVEN-ODD NUCLEI
FEASIBILITY STUDIES
FISSILE MATERIALS
FISSION
FISSIONABLE MATERIALS
FLUORIDES
FLUORINE COMPOUNDS
HALIDES
HALOGEN COMPOUNDS
HEAVY NUCLEI
HYBRID REACTORS
HYDROGEN ISOTOPES
INHIBITION
ISOTOPES
LIGHT NUCLEI
LITHIUM COMPOUNDS
LITHIUM FLUORIDES
LITHIUM HALIDES
MATERIALS
MOLTEN SALTS
NUCLEAR FUEL CONVERSION
NUCLEAR REACTION YIELD
NUCLEAR REACTIONS
NUCLEI
ODD-EVEN NUCLEI
RADIOISOTOPES
REACTOR COMPONENTS
SALTS
THERMONUCLEAR REACTOR MATERIALS
THERMONUCLEAR REACTORS
THORIUM COMPOUNDS
THORIUM FLUORIDES
TRITIUM
URANIUM 233
URANIUM ISOTOPES
YEARS LIVING RADIOISOTOPES
YIELDS