용융염 전해방법에 의한 핵연료 Sludge처리

  • Published : 1997.12.01

Abstract

핵연료의 가공공정에서 발생하는 스러지를 건식처리공정으로 회수 정제할 수 있는 건식처리 방법에 대하여 논의하고자 하였다. 건식처리방법은 수용액을 전혀 사용하지 알기 때문에 폐기물의 발생량이 습식처리방법에 비해 훨씬 줄어든다. 산화우라늄은 고온의 용융염중에서 염소개스에 의해 염소화반응을 통하여 우라늄염화물을 생성되게 되어 이들은 전기적으로 이동이 가능한 형태로 바뀌므로 전극에 선택적으로 전착될 수 있기 때문에 다른 금속이온과 분리할 수 있다. 본 보고서에서는 산화우라늄의 염소화공정, 전착공정에 대하여 기술하였고 전착된 산화물의 물리적 특성에 대하여 요약하였다.

Keywords

References

  1. ANL Report TID-8540 Pyroprocessing of reactor fuels R. Dean Pierce;L.Burris Jr.
  2. HW-62431 The preporation of uranium dioxide from a molten salt solution of uranyl chloride W.L. Lyon;E.E. Voiland
  3. HW-70,000 Plutinium recycle program Annual Repart Fiscal Year, 1961 S. Goldsmith
  4. for preseatation at the meeting, Miami,Florida, Nov. 2-7, 1986, Conf-861146-14 The application of electro refining for recovery and purifcation of fuel discharged from the Integral Fast Reactor L. Burris et al
  5. Annual Technical Report 1987, Chemical Technology Division, ANL-88-19 M.J. Steindler et al.
  6. Chem. Eng. Prog. 935 Rekindled interest in pyrometallurgical processing. L. Burris
  7. 再評價げれる 金屬燃料 FBR v.32 no.7 吉田和生等
  8. 金屬燃料 FBR サィクル v.33 no.5 常磬井守泰等
  9. 金屬燃料 FBR サィクル v.33 no.6 常磬井守泰等
  10. FBR 金屬燃料 サィクル v.33 no.6 (財)電力中央硏究所 FBR部 金屬燃料硏究室
  11. in Actinide pro-cessing, p 155(1994). Proceedings of an International Symposium held at the 123rd Annual Meeting of the Minerals, Metals, and Materials Society in SanFrancisco, California, Feb. 28-Mar. 3, 1994. Pyrometallurgical treatment of uranium are using chlorine T. Taki et al
  12. Global '93 International Conference and Technology ex:bition Future Nuclear Syste-ms:Emerging Fuel Cycles and Waste Disposal Options. Sep. 12-17, 1993, Seatle, Washington Nuclear Fuel Cycle based on dry methods for fuel reprocessing and fuel elements manufacture automated processes O.V. Skiba et al
  13. Pyroelectrochemical reprocessing of irradiated uranium-plutonium oxide Fuel for Fast Reactors A.V. Bychskor et al
  14. Radioactive waste of Fast Reactor Fuel Cycle on the base of dry technology, properties, handling and reprocessings A. P. Kirllovich et al
  15. ORNL-3693 Thermodynsmic Calculations relating to chloride volatilty processing of nuclear fuels, Ⅱ The capacity of chlorine for transporting plutonium tetrachloride vapor daring of chlorine for transporting plutonium tetrachloride vapor daring of chloring for $U_3O_8-PuO_2$ with carbon tetrachloride T.A. Gens
  16. ORNL-3586 The removal of uraninum and thorium from fueled-gaphite materials by chlorination J. L. cook R. C. Hammer
  17. ORNL-TM-1286 Chlorine volatility experimertal studies : The Reaction of $U_3O_8$ with carbon tetrachloride and mixture of carbon tetrachloride and chlorine T. A. Gens
  18. Uranium dioxide single crystals by electrodepositior R.G. Robins