Tritium release from irradiated lithium aluminate, can it be improved?
Lithium aluminate is an attractive material (in terms of its chemical, mechanical and irradiation properties) for breeding tritium in fusion reactors; however, its tritium release characteristics are not as good as those of other candidate materials. To investigate whether tritium release from lithium aluminate can be improved, we have studied the tritium release from irradiated samples of pure lithium aluminate, lithium aluminate doped with Mg, and lithium aluminate with a surface deposit of platinum. The release was studied by the temperature programmed desorption (TPD) method. Both the platinum coating and magnesium doping were found to improve the tritium release characteristics, as determined by TPD. Tritium release shifted to states with lower activation energies for the altered materials.
- Research Organization:
- Argonne National Lab., IL (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 10117682
- Report Number(s):
- ANL/CP-72865; CONF-911111-34; ON: DE92006976
- Resource Relation:
- Conference: ICFRM-5: 5th. international conference on fusion reactor materials,Clearwater, FL (United States),17-22 Nov 1991; Other Information: PBD: [1991]
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
36 MATERIALS SCIENCE
LITHIUM COMPOUNDS
TRITIUM RECOVERY
BREEDING BLANKETS
ALUMINIUM OXIDES
PHYSICAL RADIATION EFFECTS
THERMONUCLEAR REACTOR MATERIALS
TEMPERATURE DEPENDENCE
700460
700450
360606
HEATING AND FUELING SYSTEMS
FUELS
BLANKETS AND COOLING SYSTEMS
PHYSICAL PROPERTIES