Investigations of neutronics of some (D,T)-driven experimental thorium hybrid blankets with actinide multipliers
Journal Article
·
· J. Fusion Energy; (United States)
An experimental fusion-fission hybrid research facility, known as LOTUS and located at the Swiss Federal Institute of Technology (EPFL), is nearing completion. The first series of experiments are likely to commence in early 1984. A whole series of neutronic investigations are already underway to assess the feasibility of experimentally testing various blanket concepts. The following analysis centers around the use of actinide wastes as multiplier for blankets with thorium oxide fuel. The multipliers considered are UO/sub 2/, AmO/sub 2/, and CmO/sub 2/. The limited size of the experimental cavity coupled with the bulky, sealed 14 MeV (D,T)neutron generator recommends the setting up of blankets in slab geometry. The analysis encompasses the corresponding confinement geometry configurations also for the sake of perspective. It is found that the neutronic performance of thorium oxide hybrid blankets improves radically both from the standpoint of fissile fuel production and energy multiplication in the presence of transplutonium actinides. It is also reported that the specific activities of tritium and /sup 233/Pa are adequate for good counting statistics.
- Research Organization:
- Ecole Polytechnique Federate de Lavsanne, Institut de Genie Atomique, Lavsanne
- OSTI ID:
- 5194510
- Journal Information:
- J. Fusion Energy; (United States), Journal Name: J. Fusion Energy; (United States) Vol. 3:3; ISSN JFEND
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
050700 -- Nuclear Fuels-- Fuels Production & Properties
052001 -- Nuclear Fuels-- Waste Processing
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
652015 -- Nuclear Properties & Reactions
A=220 & above
Theoretical-- Nuclear Reactions & Scattering-- (-1987)
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
ACTINIDE COMPOUNDS
AMERICIUM COMPOUNDS
AMERICIUM OXIDES
BARYON REACTIONS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDING BLANKETS
BREEDING RATIO
CHALCOGENIDES
COMPUTERIZED SIMULATION
CONVERSION RATIO
CURIUM COMPOUNDS
CURIUM OXIDES
HADRON REACTIONS
HYBRID REACTORS
HYDROGEN ISOTOPES
ISOTOPE PRODUCTION
ISOTOPES
LIGHT NUCLEI
LOTUS FACILITY
MATERIALS
MATERIALS TESTING
MULTIGROUP THEORY
MULTIPLICATION FACTORS
NEUTRAL-PARTICLE TRANSPORT
NEUTRON REACTIONS
NEUTRON TRANSPORT
NEUTRON TRANSPORT THEORY
NUCLEAR REACTIONS
NUCLEI
NUCLEON REACTIONS
ODD-EVEN NUCLEI
OXIDES
OXYGEN COMPOUNDS
RADIATION TRANSPORT
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
RADIOISOTOPES
REACTOR COMPONENTS
SIMULATION
TARGETS
TESTING
THERMONUCLEAR REACTOR MATERIALS
THORIUM 232 TARGET
THORIUM COMPOUNDS
THORIUM OXIDES
TRANSPLUTONIUM COMPOUNDS
TRANSPORT THEORY
TRANSURANIUM COMPOUNDS
TRITIUM
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
WASTE PRODUCT UTILIZATION
WASTES
YEARS LIVING RADIOISOTOPES
052001 -- Nuclear Fuels-- Waste Processing
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
652015 -- Nuclear Properties & Reactions
A=220 & above
Theoretical-- Nuclear Reactions & Scattering-- (-1987)
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
ACTINIDE COMPOUNDS
AMERICIUM COMPOUNDS
AMERICIUM OXIDES
BARYON REACTIONS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDING BLANKETS
BREEDING RATIO
CHALCOGENIDES
COMPUTERIZED SIMULATION
CONVERSION RATIO
CURIUM COMPOUNDS
CURIUM OXIDES
HADRON REACTIONS
HYBRID REACTORS
HYDROGEN ISOTOPES
ISOTOPE PRODUCTION
ISOTOPES
LIGHT NUCLEI
LOTUS FACILITY
MATERIALS
MATERIALS TESTING
MULTIGROUP THEORY
MULTIPLICATION FACTORS
NEUTRAL-PARTICLE TRANSPORT
NEUTRON REACTIONS
NEUTRON TRANSPORT
NEUTRON TRANSPORT THEORY
NUCLEAR REACTIONS
NUCLEI
NUCLEON REACTIONS
ODD-EVEN NUCLEI
OXIDES
OXYGEN COMPOUNDS
RADIATION TRANSPORT
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
RADIOISOTOPES
REACTOR COMPONENTS
SIMULATION
TARGETS
TESTING
THERMONUCLEAR REACTOR MATERIALS
THORIUM 232 TARGET
THORIUM COMPOUNDS
THORIUM OXIDES
TRANSPLUTONIUM COMPOUNDS
TRANSPORT THEORY
TRANSURANIUM COMPOUNDS
TRITIUM
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
WASTE PRODUCT UTILIZATION
WASTES
YEARS LIVING RADIOISOTOPES