首页> 外文会议>International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors >Effect of UV irradiation on Corrosion Behavior of Zirconium Alloy in High Temperature Water Conditions
【24h】

Effect of UV irradiation on Corrosion Behavior of Zirconium Alloy in High Temperature Water Conditions

机译:紫外线辐射对高温水条件下锆合金腐蚀行为的影响

获取原文

摘要

The corrosion behavior of Zircaloy-4 and morphology ofoxide film formed during in-situ UV light irradiationcorrosion experiment were investigated in this study. Forin-situ UV irradiation, a circulation loop and an autoclavewith sapphire windows were specially designed for thisexperiment. Corrosion experiments were conducted at 260 °Cand 7 Mpa with deionized water condition, and thedissolved hydrogen and oxygen concentrations werecontrolled for 7 days oxidation test. Zirconium alloys areconstantly irradiated by UV through sapphire windowsengineered in the wall of autoclave.The zirconium oxide was measured from scanningelectron microscopy (SEM) results on the UV irradiatedand non-irradiated regions. The chemistry of the surfaceoxides was analyzed with energy dispersive spectroscopy(EDS). The oxide thickness and chemical depth profilesacross the oxide were investigated to study the effect ofUV on the corrosion mechanism of the oxide layer formedin pre-transition regime of zirconium alloy corrosion.
机译:锆洛伊-4的腐蚀行为及其形态在原位UV光照射期间形成的氧化膜本研究研究了腐蚀实验。为了原位紫外线辐照,循环回路和高压釜使用蓝宝石窗户专为此设计实验。腐蚀实验在260°C下进行和7MPa具有去离子水状况,以及溶解的氢和氧浓度是控制7天氧化试验。锆合金是通过蓝宝石窗户不断照射UV设计在高压釜墙上。从扫描中测量氧化锆电子显微镜(SEM)辐照的结果和非照射区域。表面的化学用能量分散光谱分析氧化物(EDS)。氧化物厚度和化学深度轮廓调查氧化物以研究效果紫外线上形成的氧化物层的腐蚀机制在锆合金腐蚀的前转换制度中。

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