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

최계천; 이창헌; 김원호

오늘 하루 그만보기

P-ISSN1225-0163
E-ISSN2288-8985
SCOPUS, ESCI, KCI

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P-ISSN 1225-0163
E-ISSN 2288-8985

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Vol.16, No.6

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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

& (2003). Study on uranium metalization yield of spent pressurized water reactor fuels and oxidation behavior of fission products in uranium metals. , 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 $600{\sim}700^{\circ}C$, 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.