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Study on uranium metalization yield of spent pressurized water reactor fuels and oxidation behavior of fission products in uranium metals
Analytical Science and Technology / Analytical Science and Technology, (P)1225-0163; (E)2288-8985
2003, v.16 no.6, pp.431-437
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(2003). Study on uranium metalization yield of spent pressurized water reactor fuels and oxidation behavior of fission products in uranium metals. Analytical Science and Technology, 16(6), 431-437.
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Abstract
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 <TEX>$600{\sim}700^{\circ}C$</TEX>, 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 <TEX>$750^{\circ}C$</TEX>. In particular, Mo was rapidly oxidized and then the alloy lost 0.76~25.22 wt% in weight.
- keywords
- metalization, lithium reduction process, quarternary alloy, oxidation behaviour
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