搜索热:失效分析 陶瓷
扫一扫 加微信
首页 > 期刊论文 > 论文摘要
Zr-Sn-Nb-Fe-Mo合金在高温高压水中的腐蚀行为
          
Corrosion Behaviors of Zr-Sn-Nb-Fe-Mo Alloy in High Temperature and High Pressure Water

摘    要
采用高压釜腐蚀试验研究了Zr-Sn-Nb-Fe-Mo合金在360 ℃/18.6 MPa去离子水中的耐蚀性,采用扫描电子显微镜(SEM)、透射电子显微镜(TEM)和激光拉曼光谱分析了合金腐蚀前后的显微组织。结果表明:合金在腐蚀300 d的腐蚀增重相比ZIRLO合金的降低了30%以上。合金中生成了均匀弥散的HCP结构的Zr(Nb,Fe)2和Zr(Nb,Fe,Mo)2第二相颗粒。腐蚀260 d后氧化膜中出现明显的平行于氧化膜/基体界面的裂纹,四方相t-ZrO2含量显著减少是氧化膜中产生裂纹并加速合金腐蚀的重要因素。添加Mo元素生成的Zr(Nb,Fe,Mo)2第二相颗粒起到了延迟氧化并减小氧化膜内应力的作用。
标    签 锆合金   腐蚀性能   第二相颗粒   氧化膜   zirconium alloy   corrosion resistance   second phase particle   oxide film  
 
Abstract
The corrosion resistance of Zr-Sn-Nb-Fe-Mo alloy in 360 ℃/18.6 MPa deionized water was studied by autoclave corrosion test. Scanning electron microscopy (SEM), transmission electron microscopy (TEM) and laser Raman spectroscopy were used to analyze the microstructure of the alloy before and after corrosion. The results showed that the corrosion weight gain of the alloy after 300 days of corrosion reduced by more than 30% compared to ZIRLO alloy. Zr(Nb,Fe)2 and Zr(Nb,Fe,Mo)2 second phase particles with HCP structure generated in the alloy were dispersed uniformly. After 260 days of corrosion, there were obvious cracks in the oxide film parallel to the oxide film/substrate interface. The significant reduction of t-ZrO2 in the tetragonal phase was an important factor that caused cracks in the oxide film and accelerated alloy corrosion. The Zr(Nb,Fe,Mo)2 second-phase particles generated by adding Mo element played a role in delaying oxidation and reducing the internal stress in the oxide film.

中图分类号 TG174   DOI 10.11973/fsyfh-202009006

 
  中国光学期刊网论文下载说明


所属栏目 核电设备的腐蚀与防护

基金项目 大型先进压水堆核电站重大专项(2019ZX06002001)

收稿日期 2020/4/30

修改稿日期

网络出版日期

作者单位点击查看


引用该论文: LU Junqiang,CHEN Fuliang,ZENG Qifeng,SHI Huigang,GUO Xianglong. Corrosion Behaviors of Zr-Sn-Nb-Fe-Mo Alloy in High Temperature and High Pressure Water[J]. Corrosion & Protection, 2020, 41(9): 32


论文评价
共有人对该论文发表了看法,其中:
人认为该论文很差
人认为该论文较差
人认为该论文一般
人认为该论文较好
人认为该论文很好
分享论文
分享到新浪微博 分享到腾讯微博 分享到人人网 分享到 Google Reader 分享到百度搜藏分享到Twitter

参考文献
【1】林诚格. 非能动安全先进压水堆核电技术[M]. 北京:原子能出版社,2010.
 
【2】刘建章. 核结构材料[M]. 北京:化学工业出版社,2007.
 
【3】CHABRETOU V,HOFFMANN P B,TRAPP-PRITSCHING S,et al. Ultra low tin quaternary alloys PWR performance-impact of tin content on corrosion resistance,irradiation growth,and mechanical properties[J]. Journal of ASTM International,2011,8(5):1-17.
 
【4】WEI J,FRANKEL P,POLATIDIS E,et al. The effect of Sn on autoclave corrosion performance and corrosion mechanisms in Zr-Sn-Nb alloys[J]. Acta Materialia,2013,61(11):4200-4214.
 
【5】PAN G,GARDE A M,ATWOOD A R. Performance and property evaluation of high-burnup optimized ZIRLOTM cladding[M]//Zirconium in the Nuclear Industry:17th Volume. West Conshohocken:ASTM International,2014:607-627.
 
【6】YUEH H K,KESTERSON R L,COMSTOCK R J,et al. Improved ZIRLOTM cladding performance through chemistry and process modifications[J]. Journal of ASTM International,2005,2(6):1-16.
 
【7】PÊCHEUR D. Oxidation of β-Nb and Zr(Fe,V)2 precipitates in oxide films formed on advanced Zr-based alloys[J]. Journal of Nuclear Materials,2000,278(2/3):195-201.
 
【8】KIM H G,PARK J Y,JEONG Y H. Ex-reactor corrosion and oxide characteristics of Zr-Nb-Fe alloys with the Nb/Fe ratio[J]. Journal of Nuclear Materials,2005,345(1):1-10.
 
【9】PARK J Y,CHOI B K,JEONG Y H,et al. Corrosion behavior of Zr alloys with a high Nb content[J]. Journal of Nuclear Materials,2005,340(2/3):237-246.
 
【10】周邦新,李强,姚美意,等. Zr-4合金氧化膜的显微组织研究[J]. 腐蚀与防护,2009,30(9):589-594,610.
 
【11】TOFFOLON-MASCLET C,BRACHET J C,JAGO G. Studies of second phase particles in different zirconium alloys using extractive carbon replica and an electrolytic anodic dissolution procedure[J]. Journal of Nuclear Materials,2002,305(2/3):224-231.
 
【12】KIM H G,JEONG Y H,KIM T H. Effect of isothermal annealing on the corrosion behavior of Zr-xNb alloys[J]. Journal of Nuclear Materials,2004,326(2/3):125-131.
 
【13】WEI T G,ZHANG L,MIAO Z,et al. Microstructure and corrosion behavior of Zr-1.0Cr-0.4Fe-xMo alloys[J]. 稀有金属:英文版,2015(2):118-124.
 
【14】ANADA H,HERB B J,NOMOTO K,et al. Effect of annealing temperature on corrosion behavior and ZrO microstructure of zircaloy-4 clading tube[M]//Zirconium in the Nuclear Industry:Eleventh International Symposium. West Conshohocken:ASTM International,1996:74-93.
 
【15】GODLEWSKI J,GROS J P,LAMBERTIN M,et al. Raman spectroscopy study of the tetragonal-to-monoclinic transition in zirconium oxide scales and determination of overall oxygen diffusion by nuclear microanalysis of O18[M]//Zirconium in the Nuclear Industry:Ninth International Symposium. West Conshohocken:ASTM International:2015:416-436.
 
【16】MOTTA A T,YILMAZBAYHAN A,COMSTOCK R J,et al. Microstructure and growth mechanism of oxide layers formed on Zr alloys studied with micro-beam synchrotron radiation[J]. Journal of ASTM International,2005,2(5):1-26.
 
相关信息
   标题 相关频次
 表面处理对Zr-Sn-Nb合金耐磨损和耐腐蚀性能的影响
 9
 Tb2TiO5-Dy2TiO5中子吸收材料的显微组织及性能
 4
 Zr-1Nb-0.1Fe-xCu合金在500℃过热水蒸气中的耐蚀性
 4
 Zr-4合金氧化膜的显微组织研究
 4
 Zr-Nb系合金在360 ℃/20 MPa溶氧水中的腐蚀行为
 4
 Zr-0.8Sn-0.35Nb-0.4Fe-0.1Cr-xBi合金在400 ℃过热蒸汽中的腐蚀行为
 3
 奥氏体不锈钢AL-6XN在超临界水中的腐蚀
 3
 淬火冷却速率对Zr-4合金显微组织和耐腐蚀性能的影响
 3
 微量硫对Zr-4合金在360 ℃ LiOH水溶液中耐腐蚀性能的影响
 3
 在高温硝酸与丙烷蒸气环境中R60702工业纯锆的腐蚀行为
 3
 316L奥氏体不锈钢在高温水中的应力腐蚀
 2
 9S75铝合金的电化学腐蚀行为及阳极氧化工艺
 2
 Haynes 282镍基合金在600~700℃超临界水中的氧化特性
 2
 HP-Nb合金转化炉管服役过程中的损伤规律
 2
 TP347H耐热钢管在超临界条件下的氧化膜结构及形成机理
 2
 Zr-2.5Nb压力管材的氧化腐蚀行为影响因素
 2
 奥氏体不锈钢在海水环境中的腐蚀疲劳裂纹扩展行为
 2
 表面粗糙度对800H合金在超临界水环境中腐蚀行为的影响
 2
 不同水化学条件下800合金传热管的均匀腐蚀性能
 2
 不同氧含量高温水中低合金钢/不锈钢堆焊层的氧化膜特性
 2
 长期服役后末级再热器12Cr1MoVG钢管的组织性能和剩余寿命评估
 2
 超临界二氧化碳环境中800H合金的均匀腐蚀行为
 2
 超声波辅助钎焊技术的研究进展
 2
 车轮转速对列车车轮磨损性能的影响
 2
 等离子表面合金化制备抗菌不锈钢及其组织与性能
 2
 低氧分压预处理对镍基合金028耐蚀性的影响
 2
 电除尘器极线腐蚀失效原因分析
 2
 电子束精炼Inconel718合金的高温氧化行为
 2
 钝化处理对Al-B4C复合材料腐蚀行为的影响
 2
 高锰钢实海环境暴露试验与实验室加速腐蚀试验结果对比
 2