カーボンダストの重水素保持特性 Deuterium Retention of Carbon Dust

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In a nuclear fusion device, plasma facing materials (PFMs) such as graphite are bombarded by extremely high heat and particle fluxes during an abnormal discharge called as disruption. As a result of the disruption, the PFMs are eroded and deposited on the wall. In the case of graphite plasma facing material, carbon dusts are produced. Flaky carbon dust was produced from isotropic graphite by electron beam evaporation. The absorption properties of deuterium in carbon dust were investigated by changing an absorption temperature (773-1173 K), time (10 min-24 hr) and deuterium gas pressure (1-100 Pa). The amount of adsorbed deuterium was evaluated by using thermal desorption spectroscopy. Deuterium was desorbed from the carbon dust at the temperature higher than 873 K in form of HD and D<SUB>2</SUB>. At the absorption temperature of 973 K and the pressure of 100 Pa, the amount of deuterium absorbed in the dust saturated within 5 hr. This saturation level was one or two orders of magnitude larger than that of isotropic graphite. The heat of solution for deuterium was 0.27 eV which was almost the same as that of isotropic graphite.

収録刊行物

  • 真空  

    真空 43(3), 377-380, 2000-03-20 

    The Vacuum Society of Japan

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各種コード

  • NII論文ID(NAID)
    10004561870
  • NII書誌ID(NCID)
    AN00119871
  • 本文言語コード
    JPN
  • 資料種別
    SHO
  • ISSN
    05598516
  • NDL 記事登録ID
    5361672
  • NDL 雑誌分類
    ZN15(科学技術--機械工学・工業--流体機械)
  • NDL 請求記号
    Z16-474
  • データ提供元
    CJP書誌  CJP引用  NDL  J-STAGE 
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