加圧水型原子炉1次冷却材環境における600合金表面での酸化機構のTEMによる直接評価  [in Japanese] Evaluation of Surface Oxidation Mechanism of Alloy 600 in a Simulated Primary Water of Pressurized Water Reactors using Analytical Transmission Electron Microscopy  [in Japanese]

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Author(s)

Journal

  • Transactions of the Atomic Energy Society of Japan

    Transactions of the Atomic Energy Society of Japan 1(2), 127-133, 2002-06-25

    日本原子力学会

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Codes

  • NII Article ID (NAID)
    10008836065
  • NII NACSIS-CAT ID (NCID)
    AA11643165
  • Text Lang
    JPN
  • Article Type
    ART
  • ISSN
    13472879
  • NDL Article ID
    6210152
  • NDL Source Classification
    ZN36(科学技術--原子力工学・工業)
  • NDL Call No.
    Z74-C788
  • Data Source
    CJP  NDL 
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