Tritium diffusion in nonmetallic solids of interest for fusion reactors. Annual progress report, August 1, 1975--August 1, 1976
Technical Report
·
OSTI ID:7334525
Tritium diffusion coefficients have been measured in a number of nonmetallic solids which have potential use as diffusion barriers or protective coatings in fusion reactors. Results have been obtained for various forms of alumina, beryllia, yttria, silicon carbide, boron carbide, glass, and pyrolytic carbon. The method of measurement involved tritium injection into solids followed by measurements of tritium release rates during heating. Measured diffusion values were significantly below the hydrogen diffusion coefficients determined for metals so nonmetallics would appear to have potential for being effective tritium barriers. Preliminary hydrogen solubility measurements were carried out for alumina and silicon carbide by measuring the amount of dissolved deuterium which was released from equilibrated specimens during heating. The technique appears to be a satisfactory means for determining temperature and pressure effects on solubility. Solubility information should be useful in determining both tritium inventories and permeation rates in CTR blanket components.
- Research Organization:
- North Carolina State Univ., Raleigh (USA). Dept. of Nuclear Engineering
- DOE Contract Number:
- E(40-1)-4721
- OSTI ID:
- 7334525
- Report Number(s):
- ORO-4721-2
- Country of Publication:
- United States
- Language:
- English
Similar Records
Tritium diffusion in nonmetallic solids of interest to fusion reactors. Annual progress report, August 1, 1976--August 1, 1977
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Technical Report
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Fri Dec 31 23:00:00 EST 1976
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OSTI ID:7285981
Tritium transport in nonmetallic solids
Conference
·
Wed Dec 31 23:00:00 EST 1975
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OSTI ID:7329474
Tritium diffusion in nonmetallic solids of interest for fusion reactors. Annual progress report, June 1, 1974--August 1, 1975
Technical Report
·
Tue Dec 31 23:00:00 EST 1974
·
OSTI ID:4162003
Related Subjects
36 MATERIALS SCIENCE
360204* -- Ceramics
Cermets
& Refractories-- Physical Properties
360603 -- Materials-- Properties
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALKALINE EARTH METAL COMPOUNDS
ALUMINIUM COMPOUNDS
ALUMINIUM OXIDES
BERYLLIUM COMPOUNDS
BERYLLIUM OXIDES
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BORON CARBIDES
BORON COMPOUNDS
CARBIDES
CARBON
CARBON COMPOUNDS
CHALCOGENIDES
DIFFUSION
ELEMENTS
GLASS
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
NONMETALS
NUCLEI
ODD-EVEN NUCLEI
OXIDES
OXYGEN COMPOUNDS
PERMEABILITY
PYROLYTIC CARBON
RADIOISOTOPES
SILICON CARBIDES
SILICON COMPOUNDS
THERMONUCLEAR REACTOR MATERIALS
TRANSITION ELEMENT COMPOUNDS
TRITIUM
YEARS LIVING RADIOISOTOPES
YTTRIUM COMPOUNDS
YTTRIUM OXIDES
360204* -- Ceramics
Cermets
& Refractories-- Physical Properties
360603 -- Materials-- Properties
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALKALINE EARTH METAL COMPOUNDS
ALUMINIUM COMPOUNDS
ALUMINIUM OXIDES
BERYLLIUM COMPOUNDS
BERYLLIUM OXIDES
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BORON CARBIDES
BORON COMPOUNDS
CARBIDES
CARBON
CARBON COMPOUNDS
CHALCOGENIDES
DIFFUSION
ELEMENTS
GLASS
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
NONMETALS
NUCLEI
ODD-EVEN NUCLEI
OXIDES
OXYGEN COMPOUNDS
PERMEABILITY
PYROLYTIC CARBON
RADIOISOTOPES
SILICON CARBIDES
SILICON COMPOUNDS
THERMONUCLEAR REACTOR MATERIALS
TRANSITION ELEMENT COMPOUNDS
TRITIUM
YEARS LIVING RADIOISOTOPES
YTTRIUM COMPOUNDS
YTTRIUM OXIDES