期刊
JOURNAL OF NUCLEAR MATERIALS
卷 327, 期 1, 页码 58-76出版社
ELSEVIER SCIENCE BV
DOI: 10.1016/j.jnucmat.2004.01.018
关键词
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The thermal diffusivity and specific heat of reactor-irradiated UO2 fuel have been measured. Starting from end-of-life conditions at various burn-ups, measurements under thermal annealing cycles were performed in order to investigate the recovery of the thermal conductivity as a function of temperature. The separate effects of soluble fission products, of fission gas frozen in dynamical solution and of radiation damage were determined. In this context, particular emphasis was given to the behaviour of samples displaying the high burn-up rim structure. Recovery stages could be thoroughly investigated in samples that were irradiated at low burn-ups and/or at high irradiation temperatures. Other samples, in particular those exhibiting the characteristic rim structure, disintegrated at temperatures slightly higher than the irradiation temperature. Finally, from a database of several thousand measurements, an accurate formula for the in-pile thermal conductivity of UO2 up to 100 GWd t(-1) was developed, taking into account all the relevant effects and structural changes induced by reactor burn-up. (C) 2004 Elsevier B.V. All rights reserved.
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