TY - JOUR
T1 - High burn-up structure of U(Mo) dispersion fuel
AU - Leenaers, Ann
AU - Van Renterghem, Wouter
AU - Van den Berghe, Sven
N1 - Score=10
PY - 2016/4/26
Y1 - 2016/4/26
N2 - The evolution of the high burn-up structure (HBS) in U(Mo) fuel irradiated up to a burn-up of ~70% 235U or ~5 1021 f/cm3 or ~120 GWd/tHM is described and compared to the observation made on LWR fuel. Scanning and transmission electron microscopy was performed on several samples having different burn-ups in order to get a better understanding of the mechanisms leading to the high burn-up structure formation. Even though there are some substantial differences between the irradiation of ceramic and U(Mo) alloy fuels (crystal structure, enrichment, irradiation temperature …), it was found that in both fuels recrystallization initiates at the same threshold and progresses in a similar way with increasing
fission density. In case of U(Mo), recrystallization leads to accelerated swelling of the fuel which could result in instability of the fuel plate.
AB - The evolution of the high burn-up structure (HBS) in U(Mo) fuel irradiated up to a burn-up of ~70% 235U or ~5 1021 f/cm3 or ~120 GWd/tHM is described and compared to the observation made on LWR fuel. Scanning and transmission electron microscopy was performed on several samples having different burn-ups in order to get a better understanding of the mechanisms leading to the high burn-up structure formation. Even though there are some substantial differences between the irradiation of ceramic and U(Mo) alloy fuels (crystal structure, enrichment, irradiation temperature …), it was found that in both fuels recrystallization initiates at the same threshold and progresses in a similar way with increasing
fission density. In case of U(Mo), recrystallization leads to accelerated swelling of the fuel which could result in instability of the fuel plate.
KW - research reactor fuel
KW - UMo
KW - recrystallization
UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/22961305
U2 - 10.1016/j.jnucmat.2016.04.035
DO - 10.1016/j.jnucmat.2016.04.035
M3 - Article
SN - 0022-3115
VL - 476
SP - 218
EP - 230
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
ER -