Study on uranium metalization yield of spent pressurized water reactor fuels and oxidation behavior of fission products in uranium metals

사용후핵연료의 우라늄 금속 전환율 측정 및 전환체 내 핵분열생성물의 산화거동 연구

  • 최계천 (한국원자력연구소, 원자력화학연구팀) ;
  • 이창헌 (한국원자력연구소, 원자력화학연구팀) ;
  • 김원호 (한국원자력연구소, 원자력화학연구팀)
  • Received : 2003.09.09
  • Accepted : 2003.11.27
  • Published : 2003.12.25


Metalization yield of uranium oxide to uranium metal from lithium reduction process of spent pressurized water reactor (PWR) fuels was measured using thermogravimetric analyzer. A reduced metal produced in the process was divided into a solid and a powder part, and each metalization yield was measured. Metalization yield of the solid part was 90.7~95.9 wt%, and the powder being 77.8~71.5 wt% individually. Oxidation behaviour of the quartemary alloy was investigated to take data on the thermal oxidation stability necessary for the study on dry storage of the reduced metal. At $600{\sim}700^{\circ}C$, weight increments of alloy of Mo, Ru, Rh and Pd was 0.40~0.55 wt%. Phase change on the surface of the alloy was started at $750^{\circ}C$. In particular, Mo was rapidly oxidized and then the alloy lost 0.76~25.22 wt% in weight.


Supported by : 과학기술부


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