トリチウム製造技術 (核融合炉でのトリチウム技術開発<特集>)  [in Japanese] Tritium Production Technology  [in Japanese]

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Author(s)

Abstract

Tritium production technology has been developed in JAERI. Using the facility for treating tritium in 40 TBq, tritium has been extracted from neutron-irradiated 6^Li-AI alloy targets by heating, collected, and stored in U-getters, while the tritium gas has been analyzed occasionally on line by radio-gas chromatography. The crude tritium gas obtained has been purified chemically and isotopically until more than 99.9% in both purities also by radio-gas chromatography. The present status of the technology has been described in this paper.

Journal

  • Journal of plasma and fusion research

    Journal of plasma and fusion research 70(1), p32-35, 1994-01

    プラズマ・核融合学会

Cited by:  1

Codes

  • NII Article ID (NAID)
    110003825906
  • NII NACSIS-CAT ID (NCID)
    AN10401672
  • Text Lang
    JPN
  • Article Type
    Journal Article
  • ISSN
    09187928
  • NDL Article ID
    3865117
  • NDL Source Classification
    ZM35(科学技術--物理学)
  • NDL Call No.
    Z15-8
  • Data Source
    CJPref  NDL  NII-ELS  NDL-Digital 
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