14MeV中性子直接問かけ法による高感度検出,(II) : ウエス系ウラン廃棄物 High-Sensitive Detection by Direct Interrogation of 14MeV Acc Neutrons, (II) : Uranium-Contained Cloth Matrix in a Waste Dram

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  Previously reported "high sensitive detection of the fissile material in a solidification waste dram by 14 MeV neutron direct interrogation method" is the skillful method effecting the neutron moderation by the waste matrix itself. About this detection method, it is already reported to confirm and to be able to achieve an effective measurement for a concrete solidification waste. Moreover, even if it is only of the metal waste that the neutron moderation is not effective in the waste matrix, it was confirmed that positional sensitivity difference can be small and highly sensitive by using the additional moderator skillfully. In this report, it is examined that this detection method can be applicable effectively or not to a cloth and papers matrix waste filling within a dram. Here, in order to understand and to evaluate the detection characteristic by the difference of the filling density and the level of the position sensitivity difference, neutron transportation calculation of the model by assuming the amount of content cloth matrix waste (which depends on the filling density) as a calculation parameter was done. The method of reducing the positional sensitivity difference was also examined. As a result, it became clear that the detection limit of the natural uranium cloth matrix waste was reached to 0.1123 Bq/g and the positional sensitivity difference was reached in ±5%.<br>

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  • 日本原子力学会和文論文誌 = Transactions of the Atomic Energy Society of Japan  

    日本原子力学会和文論文誌 = Transactions of the Atomic Energy Society of Japan 6(1), 65-72, 2007-03-25 

    Atomic Energy Society of Japan

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各種コード

  • NII論文ID(NAID)
    10018413548
  • NII書誌ID(NCID)
    AA11643165
  • 本文言語コード
    JPN
  • 資料種別
    ART
  • ISSN
    13472879
  • NDL 記事登録ID
    8772426
  • NDL 雑誌分類
    ZN36(科学技術--原子力工学・工業)
  • NDL 請求記号
    Z74-C788
  • データ提供元
    CJP書誌  CJP引用  NDL  J-STAGE 
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