...
首页> 外文期刊>Journal of Nuclear Materials: Materials Aspects of Fission and Fusion >Effect of impurities on mechanical properties of vanadium alloys under liquid-lithium environment during neutron irradiation at HFIR
【24h】

Effect of impurities on mechanical properties of vanadium alloys under liquid-lithium environment during neutron irradiation at HFIR

机译:HFIR中子辐照液锂环境下杂质对钒合金力学性能的影响

获取原文
获取原文并翻译 | 示例
   

获取外文期刊封面封底 >>

       

摘要

Vanadium alloys, including the highly purified V-4Cr-4Ti alloy, were irradiated in liquid lithium up to a damage level of 3.7 dpa in the HFIR at 425 °C and 598 °C. Neutron irradiation caused an increase of the ductile-brittle transition temperature (DBTT) and irradiation hardening was observed. Adding titanium to the V-Cr alloys was effective for increasing irradiation hardening at 425 °C. For highly purified (Zr-treated) V-4Cr-4Ti alloys the irradiation hardening was significantly reduced at both 425 °C and 598 °C. However, microstructural observations after the irradiation experiments showed that there was no significant difference in microstructure between the original and the highly purified specimens. It is suggested that the reduction of irradiation hardening in the highly purified V-4Cr-4Ti alloys was caused by the configuration and distribution of interstitial impurities in the neutron-irradiated specimen matrix. Controlling the impurities in V-4Cr-4Ti alloys has a very important effect for improving their mechanical properties that take place under neutron irradiation at around 400 °C.
机译:钒合金(包括高度纯化的V-4Cr-4Ti合金)在液态锂中在425°C和598°C的HFIR中辐照至3.7 dpa的损伤水平。中子辐照引起延性脆性转变温度(DBTT)的升高,并且观察到辐照硬化。向V-Cr合金中添加钛可有效提高425°C的辐射硬化。对于高度纯化(Zr处理)的V-4Cr-4Ti合金,在425°C和598°C时,辐射硬化明显降低。但是,辐照实验后的微观结构观察表明,原始样品和高度纯化的样品之间在微观结构上没有显着差异。有人认为,高纯V-4Cr-4Ti合金的辐照硬化减少是由于中子辐照的样品基体中间隙杂质的构型和分布所致。控制V-4Cr-4Ti合金中的杂质对于改善其在约400°C的中子辐照下产生的机械性能具有非常重要的作用。

著录项

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号