Reference

Ionic conductivity and hydrogen diffusion mechanism in lithium oxide

Ionic conductivity and hydrogen diffusion mechanism in lithium oxide. Konishi, Satoshi; Ohno, Hideo; Katsuta, Hiroji; Takeshita, Hidefumi; Yoshida, Hiroshi; Watanabe, Hitoshi; Naruse, Yuji (Tokai Res. Establ., Japan At. Energy Res. Inst., Tokai, Japan). Report, JAERI-M-82-203, 24 pp. Avail. INIS From: INIS Atomindex 1983, 14(24), Abstr. No. 10028-17-8 and 17341-24-1 are cas registry numbers. These chemicals are also mentioned in this article. 803584 (Japanese) 1983. DOCUMENT TYPE: Report CA Section: 71 (Nuclear Technology) Section cross-reference(s): 65, 76 Li2O [12057-24-8] is 1 of the candidate breeding materials for fusion reactor blankets. The ionic cond. of Li2O was measured for investigating T diffusion phenomena and for estg. the T inventory in Li2O. The self-diffusion coeff. of Li+ was obtained from expts. with Li2O single crystals and sintered pellets, using an indirect interstitial diffusion model, in which Li+ diffusion and ionic cond. are caused by Frenkel-type defects. The temp. dependence of ionic cond. and Li+ diffusion coeff. showed 3 regions of intrinsic diffusion, extrinsic diffusion, and diffusion affected by LiOH. In the latter 2 cases, Li+ diffusion is subject to the humidity in the atm. Reported T diffusion behavior in Li2O is similar to the ionic cond. Based on this result, the large differences among reported data for T diffusion can be understood. The OH- ion, which comes from moisture in the atm., is the dominant impurity in the extrinsic region. The amts. of dissolved OH- in Li2O can be estd. from the transition temp. between the extrinsic and intrinsic regions. Under a H2O vapor pressure of 10-16 Pa and temp. 500-900°, the estd. values were 10-5-10-4 OH-/Li+ and decreased with increasing temp. .

An analysis of activation and the impact of tritium breeding media and structural materials for a commercial tokamak fusion reactor design

An analysis of activation and the impact of tritium breeding media and structural materials for a commercial tokamak fusion reactor design. Jung, Jungchung (Fusion Power Program, Argonne Natl. Lab., Argonne, IL 60439, USA). Nucl. Technol.Chemicals with cas numbers 7440-50-8 and 12035-04-0 also play role./Fusion, 4(3), 566-85 (English) 1983. CODEN: NTFUDQ. ISSN: 0272-3921. DOCUMENT TYPE: Journal CA Section: 71 (Nuclear Technology) Section cross-reference(s): 55, 56 Activation anal. was conducted for several primary fusion blanket materials based on a model of a com. tokamak fusion reactor design, STARFIRE. The blanket materials studied include 2 solid T breeders, viz., Li2O [12057-24-8] and a-LiAlO2 [12003-67-7] and 4 candidate structural materials, viz., PCA stainless steel, V15Cr5Ti [82116-73-2], Ti6Al4V [12743-70-3], and Al-6063 [11121-92-9] alloys. The importance of breeder material activation is identified in terms of its impurity contents. The breeder activation is also discussed with regard to its potential for recycling and its impact on the Li resource requirements. The structural material activation is analyzed based on 2 measures, volumetric radioactivity concn. and contact biol. dose due to decay g-emission. A substantial advantage exists from a viewpoint of radioactive waste management, which is inherent in fusion reactor designs based on potential low-activation alloys such as V15Cr5Ti, Ti6Al4V, and Al-6063. From the dose standpoint, the V15Cr5Ti alloy is the only alloy for which one could realize a significant dose redn. (<2.5 mrem/h) within ~100 yr after shutdown, possibly by some extrapolation on alloy purifn. techniques. .