Annealing influence on the microstructure of irradiated U-Mo monolithic fuel foils

被引:5
作者
Di Lemma, F. G. [1 ,3 ]
Jue, J. F. [1 ]
Trowbridge, T. L. [1 ]
Smith, C. A. [2 ]
Miller, B. D. [1 ]
Keiser, D. D. [1 ]
Giglio, J. J. [1 ]
Cole, J. I. [1 ]
机构
[1] Idaho Natl Lab, POB 1625 MS 6000, Idaho Falls, ID 83415 USA
[2] Idaho Natl Lab, Glenn T Seaborg Inst, Idaho Falls, ID 83415 USA
[3] Idaho Natl Lab, Characterizat & Adv PIE Div, Mat Fuel Complex, POB 1625, Idaho Falls, ID 83415 USA
关键词
U-10Mo; Monolithic fuel; Annealing; Irradiation; Decomposition; FISSION-INDUCED RECRYSTALLIZATION; NUCLEAR-FUELS; TRANSFORMATION; PERFORMANCE; EVOLUTION; ALLOY;
D O I
10.1016/j.nme.2023.101436
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
In this study we compared the microstructure evolution of U-Mo fuel foils produced with and without heat treatment at low burn-up via advanced post-irradiation examination. The aim of this study is to observe after irradiation the ways in which the fabrication processes have influenced fuel behavior at early-stage irradiation, as for very low burn up microstructural studies are lacking. In this work it was observed that the larger grain size detected in the heat-treated samples before irradiation led to decreased grain refinement after irradiation. Grain refinement was associated with the presence of small nano-size bubbles and precipitates. This phenomenon is hypothesized to influence early fuel swelling during reactor irradiation. Grain refinement was also observed to increase in regions where & gamma;-U decomposition was present. Thus, it was enhanced in the samples fabricated without heat treatment. The heat treatment also increased the thickness of the U-Mo/Zr interface, namely of the UZr2 layer. However, the influence of this layer on fuel performance needs further investigation. On one side, it may contribute to better mechanical bonding; on the other, it may influence swelling and blistering in the interaction layer as porosity increases when this layer is increased. This was observed especially in the presence of increased area containing low Mo concentration, and thus containing a higher fraction of the & alpha;-U phase, which is highly susceptible to irradiation induced swelling. Strong evidence of reverse transformation under irradiation (& alpha;-U + & gamma;& PRIME;-U2Mo -+ bcc & gamma;-U) was observed in these samples. While the precipitates (carbides and oxide) seem to be unaffected by the irradiation at these low burnups. However, further analyses are necessary at higher burn-up to assess the exact impact different heat treatments have on fuel performance.
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页数:10
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