Electrolytic Reduction of Spent Light Water Reactor Fuel : Bench-Scale Experiment Results

抄録

A series of experiments were performed to demonstrate the electrolytic reduction of spent light water reactor fuel at bench-scale in a hot cell at the Idaho National Laboratory Materials and Fuels Complex. The process involves the conversion of oxide fuel to metal by electrolytic means, which would then enable subsequent separation and recovery of actinides via existing electrometallurgical technologies, i.e., electrorefining. Four electrolytic reduction runs were performed at bench scale using ∼500 ml of molten LiCl–1 wt% Li2O electrolyte at 650°C. In each run, ∼50 g of crushed spent oxide fuel was loaded into a permeable stainless steel basket and immersed into the electrolyte as the cathode. A spiral wound platinum wire was immersed into the electrolyte as the anode. When a controlled electric current was conducted through the anode and cathode, the oxide fuel was reduced to metal in the basket and oxygen gas was evolved at the anode. Salt samples were extracted before and after each electrolytic reduction run and analyzed for fuel and fission product constituents. The fuel baskets following each run were sectioned and the fuel was sampled, revealing an extent of uranium oxide reduction in excess of 98%.

収録刊行物

Journal of nuclear science and technology  

Journal of nuclear science and technology 44(3), 361-367, 2007-03-25 

一般社団法人 日本原子力学会

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各種コード

  • NII論文ID(NAID) :
    10018413165
  • NII書誌ID(NCID) :
    AA00703720
  • 本文言語コード :
    ENG
  • 資料種別 :
    ART
  • ISSN :
    00223131
  • NDL 記事登録ID :
    8693457
  • NDL 雑誌分類 :
    ZM35(科学技術--物理学)
  • NDL 請求記号 :
    Z53-A460
  • 収録DB :
    CJP書誌  NDL  J-STAGE