[en] The objective of this work was to examine and explain the thermochemical stability of lithium oxide during irradiation to high burnup levels. 7 refs., 4 figs

[en] The crystal structure data of Rb₄As₆ and Cs₄As₆ are given including the XRD data, atomic coordinates and thermal displacement parameters

[en] The objectives of this program are to synthesize ceramic powders and/or fabricate samples of candidate solid breeder materials for various international cooperative irradiation test programs and to characterize the mechanical properties of a number of lithium ceramics. 4 refs

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[en] The new compounds A_2ZnP_2Se_6 (A = K, Rb, Cs) were synthesized via molten salt flux syntheses. The crystals feature one-dimensional "1/_∞[ZnP_2Se_6]"2"- chains charge balanced by alkali metal ions between the chains. K_2ZnP_2Se_6 crystallizes in the monoclinic space group P2_1/c; cell parameters a = 12.537(3) Aa, b = 7.2742(14) Aa, c = 14.164(3) Aa, β = 109.63(3) , Z = 4, and V = 1216.7(4) Aa"3. Rb_2ZnP_2Se_6 and Cs_2ZnP_2Se_6 are isotypic, crystallizing in the triclinic space group P anti 1. Rb_2ZnP_2Se_6 has cell parameters of a = 7.4944(15) Aa, b = 7.6013(15) Aa, c = 12.729(3) Aa, α = 96.57(3) , β = 105.52(3) , γ = 110.54(3) , Z = 2, and V = 636.6(2) Aa"3. Cs_2ZnP_2Se_6 has cell parameters of a = 7.6543(6) Aa, b = 7.7006(6) Aa, c = 12.7373(11) Aa, α = 97.007(7) , β = 104.335(7) , γ = 109.241(6) , Z = 2, and V = 669.54(10) Aa"3. (Copyright copyright 2016 WILEY-VCH Verlag GmbH and Co. KGaA, Weinheim)

[en] The Concept of Choice of Lithium Containing Materials for Fusion Reactor Blanket is based on the following criteria: 1. the full coverage of the nuclear-physical, thermophysical, chemical, mechanical and other properties of materials; 2. the reliability of suggested blanket module designs loaded with lithium elements including conditions of tritium removal as well as heat removal; 3. feasibility of a tonnage production of the required materials that meet the first and second criteria. (author). 7 refs, 1 tab

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[en] Lithium ceramics have been considered as one of the candidates for the fabrication of tritium breeders for fusion reactors. As a part of the study program for fusion blanket development, fabrication techniques for tritium breeders which are made of lithium ceramics have been investigated and the characteristics of tritium breeders fabricated by several fabrication methods are estimated. On the other hand, lithium deposits in ore are very poor in Japan. Hence, lithium recovered from seawater should be effectively utilized for tritium breeders. In this study, γ-LiAlO₂ pellets were fabricated by solid-solid reactions between Al₂O₃ and Li₂CO₃ recovered from seawater or ore, and the characteristics of two kinds of γ-LiAlO₂ mentioned above, i.e., fabrication, physical and thermal properties, were estimated. (orig.)