14 MeV 中性子直接問かけ法による高感度検出，(II)<br/>ウエス系ウラン廃棄物

DOI Web Site 被引用文献2件 参考文献7件
  • 春山 満夫
    (独)日本原子力研究開発機構　東海研究開発センター
  • 飛田 浩
    (独)日本原子力研究開発機構　東海研究開発センター
  • 高瀬 操
    (独)日本原子力研究開発機構　東海研究開発センター
  • 森 貴正
    (独)日本原子力研究開発機構　東海研究開発センター

書誌事項

タイトル別名
  • High-Sensitive Detection by Direct Interrogation of 14 MeV Acc Neutrons, (II)<br/>Uranium-Contained Cloth Matrix in a Waste Dram
  • 14MeV チュウセイシ チョクセツ モンカケホウ ニ ヨル コウカンド ケンシュツ 2 ウエスケイ ウラン ハイキブツ

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抄録

  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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