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首页> 外文会议>Advanced materials for applications in extreme environments >Assessment of the Effect of Irradiation Temperature on the Mechanical Anisotropy of the Zr~+ Ion Irradiated Zr-2.5Nb
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Assessment of the Effect of Irradiation Temperature on the Mechanical Anisotropy of the Zr~+ Ion Irradiated Zr-2.5Nb

机译：辐照温度对Zr〜+离子辐照Zr-2.5％Nb的机械各向异性的影响评估

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摘要

We present here new information on the effect of irradiation temperature on the strength and mechanical anisotropy of Zr-2.5%Nb CANDU pressure tube material. Polished samples aligned normal to the transverse (TN), axial (AN) and radial (RN) directions of the pressure tube were irradiated at 300℃ with 8.5 MeV Zr~+ ions to assess the effect of concurrent thermal annealing of the irradiation damage. Constant-load micro-indentation creep tests were performed at 25℃ at indentation depths from 0.1 to 2.0 urn on the ion irradiated samples. The increase in the initial indentation stress with increasing levels of Zr~+ ion irradiation at 300℃ was lower than that reported earlier for similar samples exposed to Zr~+ irradiation at 25℃. While the anisotropy of the indentation stress decreased significantly with Zr~+ ion irradiation, the level of the decrease was reduced when the irradiation was performed at 300℃ compared to 25℃. The apparent activation energy △G_0 of the obstacles that limit the rate of dislocation glide during indentation creep did not change with indentation direction but did increase with increasing levels of Zr~+ ion damage. The values of △G_0 were, again, lower for samples that were irradiated at 300℃ than for those irradiated at 25℃. The observed differences in the magnitude of, and the anisotropy of, the initial indentation stress and also the decrease in the apparent activation energy of the indentation creep process of Zr-2.5%Nb samples irradiated with Zr~+ ions at 300℃ compared to those irradiated at 25℃ indicate the effect that concurrent thermal annealing has on the accumulation of irradiation damage. The effect of irradiation temperature on reducing the degree of, and the strength of, irradiation induced crystallographic damage must therefore be considered when predicting the strength and thermal creep behaviour of irradiated nuclear materials.
机译：我们在这里介绍有关辐照温度对Zr-2.5％Nb CANDU压力管材料的强度和机械各向异性的影响的新信息。垂直于压力管的横向（TN），轴向（AN）和径向（RN）排列的抛光样品在300℃下用8.5 MeV Zr〜+离子辐照，以评估同时进行热退火对辐照损伤的影响。在25℃，压痕深度为0.1到2.0微米的离子辐照样品上进行了恒载荷微压痕蠕变试验。 Zr〜+离子辐照水平在300℃时，初始压痕应力的增加幅度低于25℃时暴露于Zr〜+辐照的类似样品。当Zr〜+离子辐照时，压痕应力的各向异性显着降低，而在25℃辐照时，在300℃辐照时，压应力的各向异性降低了。限制压痕蠕变过程中位错滑移速率的障碍物的表观活化能△G_0不会随压痕方向变化而随Zr〜+离子损伤程度的增加而增加。再者，在300℃下照射的样品的△G_0值比在25℃下照射的样品的△G_0值低。与Zr〜+离子辐照的Zr-2.5％Nb样品在300℃辐照时，观察到的初始压痕应力大小和各向异性的差异，以及压痕蠕变过程的表观活化能降低。 25℃辐照表明同时进行热退火对辐照损伤的积累有影响。因此，在预测被辐照核材料的强度和热蠕变行为时，必须考虑辐照温度对降低辐照引起的结晶学破坏程度和强度的影响。

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  • 会议地点 Boston MA(US);Boston MA(US);Boston MA(US);Boston MA(US)
  • 作者

    Bipasha Bose; Robert J. Klassen;

  • 作者单位

    Department of Mechanical and Materials Engineering, Faculty of Engineering, University of Western Ontario, London, Ontario, N6A 5B9, Canada;

    Department of Mechanical and Materials Engineering, Faculty of Engineering, University of Western Ontario, London, Ontario, N6A 5B9, Canada;

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  • 正文语种 eng
  • 中图分类 工程材料一般性问题;
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