TY - JOUR
T1 - The melting temperature of irradiated oxide fuel
AU - Komatsu, Junji
AU - Tachibana, Toshimichi
AU - Konashi, Kenji
PY - 1988/6
Y1 - 1988/6
N2 - The melting temperature of oxide fuel is generally considered to decrease with increasing of burnup because of the buildup of fission products. Melting temperatures were measured for UO2 and (U, Pu)O2 fuels. The (U, Pu)O2 specimens were irradiated to a burnup of 110 GWd/t in FBR. The solidus temperatures of (U, Pu)O2 were almost independent of burnup up to 50 GWd/t. The melting temperatures were correlated with Pu content, oxygen-to-metal ratio of the fuel and burnup by ideal solution theory.
AB - The melting temperature of oxide fuel is generally considered to decrease with increasing of burnup because of the buildup of fission products. Melting temperatures were measured for UO2 and (U, Pu)O2 fuels. The (U, Pu)O2 specimens were irradiated to a burnup of 110 GWd/t in FBR. The solidus temperatures of (U, Pu)O2 were almost independent of burnup up to 50 GWd/t. The melting temperatures were correlated with Pu content, oxygen-to-metal ratio of the fuel and burnup by ideal solution theory.
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U2 - 10.1016/0022-3115(88)90116-X
DO - 10.1016/0022-3115(88)90116-X
M3 - Article
AN - SCOPUS:0024019859
SN - 0022-3115
VL - 154
SP - 38
EP - 44
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
IS - 1
ER -