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Title: Aspects of tritium release from neutron-irradiated lithium oxide

Thesis/Dissertation ·
OSTI ID:5701564

Lithium oxide is a compound that may satisfy tritium breeding requirements with enhanced safety in proposed fusion reactors. An experimental program was developed to establish tritium release characteristics for Li/sub 2/O that consisted of 1) test material definition, 2) tritium generation, and 3) study of the tritium release process in an out-of-reactor tritium detection system. Source material was obtained from single crystal solidified melts of > 99.4 wt.% purity. Representative parameters of the lithium oxide were obtained through two-dimensional SEM image, gas-adsorption, density, and neutron activation analyses. Ampoules of 10-30 mg mass lithium oxide were irradiated to a fluence of 6.8 x 10/sup 16/ in the University of Wisconsin Nuclear Reactor. Small masses (5-10 mg) of the tritiated lithium oxide were processed in a thermal extraction apparatus at 673-973 K under varying helium (33-67 cm/sup 3//min) and hydrogen (0-2 cm/sup 3//min) sweep gas conditions. It was established from late-stage release curves that solid-phase diffusion of tritium ultimately controls the overall release process.

Research Organization:
Wisconsin Univ., Madison (USA)
OSTI ID:
5701564
Resource Relation:
Other Information: Thesis (Ph. D.)
Country of Publication:
United States
Language:
English