Melting Temperature of Mixed Oxide Fuels for Fast Reactors

概要

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Alternation of the melting temperature of irradiated mixed oxide (MOX) fuel in fast reactors with progress of burnup was determined in relation to the actinide fractions contained and of the oxygen-to-metal (O/M) ratio. Based on ideal solution models of UO2–PuO2 and UO2–PuO2–Am2O3 systems and on correlations obtained of the measured melting with O/M ratio and with burnup, an equation was derived expressing the estimated melting temperature Trev (K) as function of the factors mentioned above that affect the temperature:Trev=3,138−497X1+60X12−(1,000−2,850X1)(2.00−X4)−(1,206−782X1)X2 −(1.06−1.43X1)X3+0.0008((1.06−1.43X1)⁄0.66)1.5X32,where X1 is the plutonium fraction (Pu/(Pu+U)), X2 the americium fraction (Am/(Pu+U+Am)), X3 the burnup (GWd/t), and X4 the O/M ratio (−) (not exceeding 2.00). Toward advanced stage of burnup, the tendency of irradiated fuel melting temperature to lower with burnup progress presented a tendency to level off its rate of descent.
一般社団法人日本原子力学会の論文
2002-07-25