锆合金中的氢化锆在400℃过热蒸汽中的氧化行为
Oxidation Behavior of Zirconium Hydride in Zirconium Alloys in Superheated Steam at 400?C
DOI: 10.12677/NST.2017.52011, PDF, HTML, 下载: 1,777  浏览: 3,212  国家自然科学基金支持
作者: 毛亚婧, 段文荣, 黄 娇, 姚美意*, 张金龙, 周邦新:上海大学材料研究所,上海;上海大学微结构重点实验室,上海;袁改焕, 高 博, 孙国成:国核宝钛锆业股份公司,陕西 宝鸡
关键词: 金属材料氢化锆氧化应力再取向Metallic Material Zirconium Hydride Oxidation Stress Reorientation
摘要: 采用气相渗氢法制备了SZA-4合金预渗氢样品,通过高压釜腐蚀实验研究了锆合金中氢化锆的氧化行为。结果表明:在氧化膜/金属(O/M)界面附近金属基体中较大张应力的作用下,基体中已存在的氢化锆发生应力再取向,近似平行于O/M界面的面心立方(fcc)结构的δ-ZrH1.66变为垂直于O/M界面的面心四方(fct)结构的ε-ZrH2。ε-ZrH2氧化速度比α-Zr基体快,氧化为单斜ZrO2(m-ZrO2)。
Abstract: To investigate the oxidation of zirconium hydride, the corrosion test on pre-hydrided SZA-4 alloy prepared by gaseous hydrogen charging method was performed in an autoclave. Results showed that under high tensile stress produced in α-Zr matrix at the oxide/metal (O/M) interface, hydride reorientation took place and led to the transition from δ-ZrH1.66 (fcc structure) parallel to the O/M interface to ε-ZrH2 (fct structure) perpendicular to the O/M interface. ε-ZrH2 oxidized faster than α-Zr matrix, and was oxidized to m-ZrO2(monoclinic ZrO2).
文章引用:毛亚婧, 段文荣, 袁改焕, 高博, 孙国成, 黄娇, 姚美意, 张金龙, 周邦新. 锆合金中的氢化锆在400℃过热蒸汽中的氧化行为[J]. 核科学与技术, 2017, 5(2): 77-83. https://doi.org/10.12677/NST.2017.52011

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