鉄系金属廃棄物の溶融・造塊時における放射性核種の移行挙動 Radionuclide Transport Behavior During Melting and Ingot Making of Ferrous Waste

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  The development of technologies to recycle low-level radioactive waste from decommissioned nuclear facilities is a key issue from the view point of reducing waste and the recovering natural resources. Radionuclide tranport behavior during melting is an important factor in the safety of radioactive metal (scrap) recycling. We obtained data on radionuclide transport from basic melting tests conducted in JAERI, and analyzed the data by using a statistical analysis method. As a result, it is found that the transport of Mn, Zn and Sr is mainly dominated by oxydation-reduction reaction between slag and molten metal and is explained on the basis of oxygen concentration in slag. On the other hand, the transport behavior of Cs is not explained by oxydation-reduction reaction. It is assumed that the partitioning of Cs to the off-gas is affected by its evaporation and restraint in sillicic acid network structure.

収録刊行物

  • 鋳造工学 = Journal of Japan Foundry Engineering Society  

    鋳造工学 = Journal of Japan Foundry Engineering Society 68(8), 644-649, 1996-08-25 

    Japan Foundry Engineering Society

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各種コード

  • NII論文ID(NAID)
    10002113837
  • NII書誌ID(NCID)
    AN10514770
  • 本文言語コード
    JPN
  • 資料種別
    ART
  • ISSN
    13420429
  • NDL 記事登録ID
    4021293
  • NDL 雑誌分類
    ZP41(科学技術--金属工学・鉱山工学)
  • NDL 請求記号
    Z17-277
  • データ提供元
    CJP書誌  NDL  J-STAGE 
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