4.7 Article

The effect of irradiation temperature on damage structures in proton-irradiated zirconium alloys

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JOURNAL OF NUCLEAR MATERIALS
卷 514, 期 -, 页码 358-367

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ELSEVIER SCIENCE BV
DOI: 10.1016/j.jnucmat.2018.12.006

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  1. EPSRC [EP/I005420/1]
  2. National Nuclear Laboratory

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A study into the effects of irradiation temperature on the damage structures that form during protonirradiation has been carried out on two commercial Zr alloys in order to develop a more mechanistic understanding of the effect of niobium on dislocation loop evolution. The two Zr alloys (Zircaloy-2 and Low-Sn ZIRLO (TM)) were proton irradiated to a damage level of similar to 2 dpa at 280 degrees C, 350 degrees C and 450 degrees C. Detailed dislocation analysis was carried out using on-axis bright-field scanning transmission electron microscopy combined with spectral imaging and synchrotron x-ray line profile analysis. The analysis revealed a significant difference in the effect of irradiation temperature on loop size between the two alloys. In the case of the Nb-free Zr-alloy (Zircaloy-2), an increase in irradiation temperature results in a marked increase in a-loop diameter, by a factor of similar to 7.5 from 280 to 450 degrees C, and a stark decrease in the dislocation line density. In contrast, the Nb-containing Zr-alloy (Low-Sn ZIRLO (TM)) showed very little variation of loop size and line density over the same radiation temperature range. The STEM-based spectral imaging revealed irradiation-induced nano-clustering found throughout the matrix in Low-Sn ZIRLO (TM), which is not present in the case of Zircaloy-2. Therefore, it is proposed that Nb plays a crucial role in the evolution of dislocation loops in Zr through the formation of irradiation precipitation throughout the matrix. (C) 2018 Elsevier B.V. All rights reserved.

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