Trade-off study of liquid metal self-cooled blankets
Conference
·
· Fusion Technol.; (United States)
OSTI ID:6833055
A trade-off study of liquid metal self-cooled blankets was carried out to define the performance of these blankets and to determine the potential to operate at the maximum possible values of the performance parameters. The main parameters considered during the course of this study were the tritium breeding ratio (TBR), the blanket energy multiplication factor, the energy fraction lost to the shield, the lithium-6 enrichment in the breeder material, the total blanket thickness, the reflector material selection, and the compositions of the different blanket zones. The primary results of the study are as follows: a) the lithium-lead blanket achieves a higher TBR with a smaller blanket thickness relative to the lithium blanket; b) the lithium blanket generates more energy per fusion neutron relative to the lithium-lead blanket; c) among the possible reflector materials, the carbon reflector produces the highest TBR; d) the high-Z reflector materials (Mo, Cu, W, or steel) generate more energy per fusion neutron and produce smaller TBRs relative to the carbon reflector; e) lithium-6 enrichment is required for the lithium-lead blanket to reduce the total blanket thickness; and f) the energy deposition per fusion neutron reaches a saturation as the blanket thickness, the fraction of the high-Z material in the reflector, or the reflector zone thickness increases (this allows one to design the blanket for a specific TBR without reducing the energy production).
- Research Organization:
- Argonne National Lab., 9700 South Cass Avenue, Argonne, IL 60439
- OSTI ID:
- 6833055
- Report Number(s):
- CONF-860652-
- Conference Information:
- Journal Name: Fusion Technol.; (United States) Journal Volume: 10:3
- 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
ABSORPTION
ALKALI METAL ISOTOPES
ALLOYS
BARYONS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDING BLANKETS
BREEDING RATIO
CARBON
CONVERSION RATIO
COOLANTS
COPPER
DIMENSIONS
ELEMENTARY PARTICLES
ELEMENTS
ENERGY ABSORPTION
ENERGY LOSSES
FERMIONS
FLUIDS
HADRONS
HYDROGEN ISOTOPES
IRON ALLOYS
IRON BASE ALLOYS
ISOTOPES
LIGHT NUCLEI
LIQUID METALS
LIQUIDS
LITHIUM 6
LITHIUM ISOTOPES
LOSSES
MATERIALS
METALS
MOLYBDENUM
MULTIPLICATION FACTORS
NEUTRONS
NONMETALS
NUCLEI
NUCLEONS
ODD-EVEN NUCLEI
ODD-ODD NUCLEI
PERFORMANCE TESTING
RADIOISOTOPES
REACTOR COMPONENTS
SHIELDS
STABLE ISOTOPES
STEELS
TESTING
THERMONUCLEAR REACTOR MATERIALS
THERMONUCLEAR REACTORS
THICKNESS
TRANSITION ELEMENTS
TRITIUM
TUNGSTEN
YEARS LIVING RADIOISOTOPES
700201* -- Fusion Power Plant Technology-- Blanket Engineering
ABSORPTION
ALKALI METAL ISOTOPES
ALLOYS
BARYONS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDING BLANKETS
BREEDING RATIO
CARBON
CONVERSION RATIO
COOLANTS
COPPER
DIMENSIONS
ELEMENTARY PARTICLES
ELEMENTS
ENERGY ABSORPTION
ENERGY LOSSES
FERMIONS
FLUIDS
HADRONS
HYDROGEN ISOTOPES
IRON ALLOYS
IRON BASE ALLOYS
ISOTOPES
LIGHT NUCLEI
LIQUID METALS
LIQUIDS
LITHIUM 6
LITHIUM ISOTOPES
LOSSES
MATERIALS
METALS
MOLYBDENUM
MULTIPLICATION FACTORS
NEUTRONS
NONMETALS
NUCLEI
NUCLEONS
ODD-EVEN NUCLEI
ODD-ODD NUCLEI
PERFORMANCE TESTING
RADIOISOTOPES
REACTOR COMPONENTS
SHIELDS
STABLE ISOTOPES
STEELS
TESTING
THERMONUCLEAR REACTOR MATERIALS
THERMONUCLEAR REACTORS
THICKNESS
TRANSITION ELEMENTS
TRITIUM
TUNGSTEN
YEARS LIVING RADIOISOTOPES