Published May 1983 | Version v1
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Status of lithium oxide blanket material research

  • 1. Japan Atomic Energy Research Inst., Tokai Research Establishment (Japan)

Description

Preparation of Li2O pellets has been accomplished by the press-sintering method, using Li2O powder which was produced by thermal decomposition of Li2CO3 as a starting material. The reaction between Li2O and moisture-containing air was preliminarily studied on the view of handling pellets. Li2O has relatively high thermal conductivity compared with other solid blanket candidates. Its thermal expansion coefficient was also measured. Thermodynamical properties on solubility and diffusivity of hydrogen in Li2O pellet were measured by an equilibrium-quenching and hot-extraction method. Dissolved amount of hydrogen was 2 to 4 wppm at 105 Pa of hydrogen pressure in the temperature range 770 to 970 K. On the other hand, the amount of hydrogen existing in Li2O as an atomic state was extremely little according to an electron spin resonance measurement. For the compatibility of Li2O with container materials, the incipient reactions with Cr, Fe and Ni were studied by 4He-backscattering method. In addition, the reactions of Li2O with commercial alloys were examined and a comparative evaluation was deduced. Tritium produced in Li2O by the 6Li(n,α)T reaction was released mostly in the form of HTO(g) through heat treatment (473-870 K) under vacuum. The diffusion coefficients were determined for Li2O powders and pellets in different neutron fluences (1015 to 1017 n/cm2). The rate-determining step of HTO(g) release from Li2O was found to be diffusion of tritium in the solid. In-pile tests of tritium release from Li2O pellets are planned in thermal neutron fluences (1018 to 1020 n/cm2) at present. (author).

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Part of:
Fusion Reactor Design and Technology. Vol. 2. Proceedings of the Third Technical Meeting

Additional details

Publishing Information

Publisher
IAEA
Imprint Place
Vienna (International Atomic Energy Agency (IAEA))
ISBN
92-0-131183-4
Imprint Title
Fusion Reactor Design and Technology. Vol. 2. Proceedings of the Third Technical Meeting
Imprint Pagination
502 p.
Series
Proceedings Series
Journal Page Range
p. 319-332
ISSN
0074-1884

Conference

Title
3. Technical Committee Meeting and Workshop on Fusion Reactor Design and Technology
Dates
5-16 Oct 1981
Place
Tokyo (Japan)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
53051815
Subject category
S75: CONDENSED MATTER PHYSICS, SUPERCONDUCTIVITY AND SUPERFLUIDITY; S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DIFFUSION; HEAT RESISTING ALLOYS; KINETIC EQUATIONS; LITHIUM OXIDES; SPECIFIC HEAT; THERMAL EXPANSION
Descriptors DEC
ALKALI METAL COMPOUNDS; ALLOYS; CHALCOGENIDES; EQUATIONS; EXPANSION; HEAT RESISTANT MATERIALS; LITHIUM COMPOUNDS; MATERIALS; OXIDES; OXYGEN COMPOUNDS; PHYSICAL PROPERTIES; THERMODYNAMIC PROPERTIES

Optional Information

Notes
18 refs., 12 figs., 2 tabs.; This record replaces 14773846 Imprint:In two volumes
Secondary number(s)
IAEA-TC--392/57