The melting (solidus) temperatures were measured for fuel simulating burnup
s of 50, 90, 130, 170, 210 and 250 GWd/t (SIMFUEL) which were added non-rad
ioactive soluble fission products (FPs) to unirradiated fast reactor MOX fu
el. The melting temperatures for fuels of 250 GWd/t which were blended non-
radioactive soluble FPs and irradiated fuels of 110.6 and 119.0 GWd/t were
also compared to the SIMFUEL of 250 GWd/t. The melting temperature decrease
of the SIMFUEL tended to saturate with increasing burnup and the melting t
emperatures appeared virtually constant above 170 GWd/t. An equation for me
lting temperature was obtained from the proposed equation in the previous r
eport by revising the coefficient of the fifth term:
T-m = 3, 133.8 - 460X(1) - 980X(2) - 0.66X(3) + 0.0008(X-3)(2),
where T-m is the expected melting temperature (K); X-1 the plutonium fracti
on (Pu/(Pu+U)), X-2 the americium fraction (Am/(Pu+U+Am)), and X-3 the burn
up (GWd/t).
After the temperature measurement, the radial distribution of eight FP oxid
e additives in SIMFUEL of 250 GWd/t was measured by X-ray microanalysis. Re
lative characteristic X-ray intensities of Zr, Ce, La and Sr had the same r
adial profiles, whilst they did not correspond to the X-ray intensity profi
les of Nd and Y.