Thermal conductivities for sintered and sphere-pac Li/sub 2/O and gamma-LiA1O/sub 2/ solid breeders with and without irradiation effects
Journal Article
·
· Fusion Technol.; (United States)
OSTI ID:5793012
Thermal conductivities (k,K /sub eff/) have been estimated for sintered and sphere-pac Li/sub 2/O and ..gamma..-LiAtO/sub 2/ with and without neutron irradiation effects. The estimation is based on (a) data from unirradiated UO/sub 2/, Li/sub 2/O, and ..gamma..-LiAlO/sub 2/; (b) data from irradiated dielectric insulator materials; and (c) relatively simple physical models. Comparison of model predictions with limited ex- and in-reactor data found reasonable agreement, thus lending credence for their use in design applications. The impact of thermal conductivities on tritium breeding and power generation in fusion solid breeder blankets is briefly highlighted.
- Research Organization:
- Argonne National Laboratory, Materials Science and Technology Division, Argonne, IL
- OSTI ID:
- 5793012
- Journal Information:
- Fusion Technol.; (United States), Journal Name: Fusion Technol.; (United States) Vol. 7:3; ISSN FUSTE
- Country of Publication:
- United States
- Language:
- English
Similar Records
Thermal conductivities for sintered and sphere-pac Li/sub 2/O and. gamma. /sup -/LiAlO/sub 2/ solid breeders with and without irradiation effects
Thermal conductivities for sintered and sphere-pac Li/sub 2/O and. gamma. -LiAlO/sub 2/ solid breeders with and without irradiation effects
Solid tritium breeder materials-Li/sub 2/O and LiAlO/sub 2/: a data base review
Technical Report
·
Sun Jul 01 00:00:00 EDT 1984
·
OSTI ID:6332188
Thermal conductivities for sintered and sphere-pac Li/sub 2/O and. gamma. -LiAlO/sub 2/ solid breeders with and without irradiation effects
Journal Article
·
Wed May 01 00:00:00 EDT 1985
· Fusion Technol.; (United States)
·
OSTI ID:5520547
Solid tritium breeder materials-Li/sub 2/O and LiAlO/sub 2/: a data base review
Journal Article
·
Sun Sep 01 00:00:00 EDT 1985
· Fusion Technol.; (United States)
·
OSTI ID:5791055
Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700205* -- Fusion Power Plant Technology-- Fuel
Heating
& Injection Systems
ACTINIDE COMPOUNDS
ALKALI METAL COMPOUNDS
ALUMINIUM COMPOUNDS
ALUMINIUM OXIDES
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDING
BREEDING BLANKETS
CHALCOGENIDES
COMPUTERIZED SIMULATION
DESIGN
DIELECTRIC MATERIALS
HYDROGEN ISOTOPES
IRRADIATION
ISOTOPES
LIGHT NUCLEI
LITHIUM COMPOUNDS
LITHIUM OXIDES
MATERIALS
MATERIALS TESTING
NEUTRON FLUENCE
NUCLEAR FUEL CONVERSION
NUCLEI
ODD-EVEN NUCLEI
OXIDES
OXYGEN COMPOUNDS
PHYSICAL PROPERTIES
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
RADIOISOTOPES
REACTOR COMPONENTS
SIMULATION
SINTERED MATERIALS
TESTING
THERMAL CONDUCTIVITY
THERMODYNAMIC PROPERTIES
THERMONUCLEAR REACTOR MATERIALS
THERMONUCLEAR REACTORS
TRITIUM
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
YEARS LIVING RADIOISOTOPES
700205* -- Fusion Power Plant Technology-- Fuel
Heating
& Injection Systems
ACTINIDE COMPOUNDS
ALKALI METAL COMPOUNDS
ALUMINIUM COMPOUNDS
ALUMINIUM OXIDES
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDING
BREEDING BLANKETS
CHALCOGENIDES
COMPUTERIZED SIMULATION
DESIGN
DIELECTRIC MATERIALS
HYDROGEN ISOTOPES
IRRADIATION
ISOTOPES
LIGHT NUCLEI
LITHIUM COMPOUNDS
LITHIUM OXIDES
MATERIALS
MATERIALS TESTING
NEUTRON FLUENCE
NUCLEAR FUEL CONVERSION
NUCLEI
ODD-EVEN NUCLEI
OXIDES
OXYGEN COMPOUNDS
PHYSICAL PROPERTIES
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
RADIOISOTOPES
REACTOR COMPONENTS
SIMULATION
SINTERED MATERIALS
TESTING
THERMAL CONDUCTIVITY
THERMODYNAMIC PROPERTIES
THERMONUCLEAR REACTOR MATERIALS
THERMONUCLEAR REACTORS
TRITIUM
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
YEARS LIVING RADIOISOTOPES