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Fabrication and characterization of $$^{6}$$Li-enriched Li$$_{2}$$TiO$$_{3}$$ pebbles for a high Li-burnup irradiation test

Tsuchiya, Kunihiko ; Kawamura, Hiroshi

Lithium titanate (Li$$_{2}$$TiO$$_{3}$$) pebbles are considered to be a candidate material of tritium breeders for fusion reactor from viewpoints of easy tritium release at low temperatures (about 300$$^{circ}$$) and chemical stability. In the present study, trial fabrication tests of $$^{6}$$Li-enriched Li$$_{2}$$TiO$$_{3}$$ pebbles of 1mm in diameter were carried out by a wet process with a dehydration reaction, and characteristics of the $$^{6}$$Li-enriched Li$$_{2}$$TiO$$_{3}$$ pebbles were evaluated for preparation of a high Li-burnup test in a testing reactor. Powder of 96at% $$^{6}$$Li-enriched Li$$_{2}$$TiO$$_{3}$$ was prepared by a solid state reaction, and two kinds of $$^{6}$$Li-enriched Li$$_{2}$$TiO$$_{3}$$ pebbles, namely un-doped and TiO$$_{2}$$-doped Li$$_{2}$$TiO$$_{3}$$ pebbles, were fabricated by the wet process. Based on results of the pebble fabrication tests, two kinds of $$^{6}$$Li-enriched Li$$_{2}$$TiO$$_{3}$$ pebbles were successfully fabricated with target values (density : 80-85%T.D., grain size : $$<$$5$$mu$$m, diameter : 0.85-1.18mm). Physical, chemical and mechanical properties of these pebbles were also evaluated before neutron irradiation tests. Sphericity of these Li$$_{2}$$TiO$$_{3}$$ pebbles was a satisfying value of about 1.05. Contact strength of these pebbles was about 6300MPa, which was almost the same as that of the Li$$_{2}$$TiO$$_{3}$$ pebbles with natural Li.

Language

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English

Report No.

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JAEA-Technology 2006-047

Pages

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18 Pages

Publication Year/Month

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2006/10

Patent information

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PDF

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JAEA-Technology-2006-047.pdf:2.2MB

Paper URL

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https://doi.org/10.11484/jaea-technology-2006-047

Keywords

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no keyword

Research Facility

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Press Release

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Article of JAEA R&D Review

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Cooperating Institute

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Other institute's report number

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