镍基合金堆焊层在除氧和含氢高温水中氧化膜的性能
Characteristics of Oxide Films Formed on Ni-base Alloy Cladding in Deaerated and Hydrogenated High Temperature Water Environment
摘 要
研究了镍基合金堆焊层在模拟压水堆一回路水中生成的表面氧化膜的特性，对比了镍基合金在除氧水（溶解氧含量<5 μg/L）和含氢水（溶解氢含量约为2.6 mg/L）中生成的氧化膜的异同。结果表明：在325℃下浸泡146 h后，除氧水中镍基合金表面生成了稀疏分布的氧化物颗粒，含氢水中镍基合金表面则几乎无氧化物颗粒，只生成了一层黑色的氧化膜。含氢水中，在堆焊层厚度方向上越靠近堆焊层-基体熔合线，镍基合金表面生成的氧化物颗粒也越密集，其氧含量也越高，这表明堆焊层过渡区材料特性与高温水中氧化膜具有相关性。
堆焊层
镍基合金
高温水
氧化膜
pressurized water reactor
cladding
nickel-base alloy
high temperature water
oxide film
Abstract
The characteristics of oxide films formed on Ni-base alloy cladding in simulated pressurized water reactor primary water environments were studied. The oxide films formed in deaerated (dissolved oxygen concentration <5 μg/L) and hydrogenated (dissolved hydrogen concentration was 2.6 mg/L) water environments were compared. The results showed that after immersion at 325℃ for 146 h, oxide particles distributed on the surface of nickel-base alloy sparsely in deaerated water, while in hydrogenated water there was only a dark oxide film without significant outer layer oxide particles. In hydrogenated water, the closer to the overlaying layer-matrix fusion line in the thickness direction of the weld layer, the denser the oxide partides on the surface of the nickel-base alloy, and the higher the oxygen content. The correlation between the material properties in the cladding transition zone and the oxide film properties formed in high temperature water existed.
中图分类号 TG170 DOI 10.11973/fsyfh-201807009
所属栏目 核电设备的腐蚀与防护
基金项目 国家自然科学基金（51771107）；上海市经济信息委员会产学研合作项目（221715003）；上海电气核电设备有限公司科技创新项目
收稿日期 2017/9/18
修改稿日期
网络出版日期
作者单位点击查看
引用该论文: JIA Yibo,LIN Sichun,LÜ,Zhanpeng,MA Jiarong,XIONG Qi,LI Hongjuan,CHEN Junjie,LI Shuangyan,ZHANG Maolong. Characteristics of Oxide Films Formed on Ni-base Alloy Cladding in Deaerated and Hydrogenated High Temperature Water Environment[J]. Corrosion & Protection, 2018, 39(7): 530
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
参考文献
【1】李光福. 压水堆压力容器接管-主管安全端焊接件在高温水中失效案例和相关研究[J]. 核技术,2013,36(4):232-237.
【2】LI G F,CONGLETON J. Stress corrosion cracking of a low alloy steel to stainless steel transition weld in PWR primary waters at 292℃[J]. Corrosion Science,2000:1005-1021.
【3】JENSSEN A,NORRGÅRD K,LAGERSTRÖM J,et al. Assessment of cracking in dissimilar metal welds[C]//10th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors NACE. Houston,TX:[s.n.],2001.
【4】丁杰,张志明,王俭秋,等. 三代核电接管安全端异种金属焊接接头的显微表征[J]. 金属学报,2015,51(4):425-439.
【5】MACHET A,GALTAYRIES A,MARCUS P,et al. XPS study of oxides formed on nickel-base alloys in high-temperature and high-pressure water[J]. Surface & Interface Analysis,2002,34(1):197-200.
【6】高欣,吴欣强,关辉,等. 高温高压水环境中腐蚀产物膜的研究现状[J]. 腐蚀科学与防护技术,2007,19(2):110-113.
【7】MASLAR J E,HURST W S,BOWERS W J,et al. In situ Raman spectroscopic investigation of aqueous iron corrosion at elevated temperatures and pressures[J]. Journal of the Electrochemical Society,2000,147(7):2532-2542.
【8】KIM J,CHOI K J,CHI B B,et al. In situ Raman spectroscopic analysis of surface oxide films on Ni-base alloy/low alloy steel dissimilar metal weld interfaces in high temperature water[J]. Journal of Nuclear Materials,2014,449(1/3):181-187.
【9】KIM J H,HWANG I S. Development of an in situ Raman spectroscopic system for surface oxide films on metals and alloys in high temperature water[J]. Nuclear Engineering & Design,2014,235(9):1029-1040.
【10】TERACHI T,TOTSUKA N,YAMADA T,et al. Influence of dissolved hydrogen on structure of oxide film on alloy 600 formed in primary water of pressurized water reactors[J]. Journal of Nuclear Science & Technology,2003,40(7):509-516.
【11】SENNOUR M,MARCHETTI L,MARTIN F,et al. A detailed TEM and SEM study of Ni-base alloys oxide scales formed in primary conditions of pressurized water reactor[J]. Journal of Nuclear Materials,2010,402:147-156.
【12】TERACHI T,YAMADA T, TOMOKI M,et al. Corrosion behavior of stainless steels in simulated PWR primary water-effect of chromium content in alloys and dissolved hydrogen[J]. Journal of Nuclear Science & Technology,2008,45(10):975-984.
【2】LI G F,CONGLETON J. Stress corrosion cracking of a low alloy steel to stainless steel transition weld in PWR primary waters at 292℃[J]. Corrosion Science,2000:1005-1021.
【3】JENSSEN A,NORRGÅRD K,LAGERSTRÖM J,et al. Assessment of cracking in dissimilar metal welds[C]//10th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors NACE. Houston,TX:[s.n.],2001.
【4】丁杰,张志明,王俭秋,等. 三代核电接管安全端异种金属焊接接头的显微表征[J]. 金属学报,2015,51(4):425-439.
【5】MACHET A,GALTAYRIES A,MARCUS P,et al. XPS study of oxides formed on nickel-base alloys in high-temperature and high-pressure water[J]. Surface & Interface Analysis,2002,34(1):197-200.
【6】高欣,吴欣强,关辉,等. 高温高压水环境中腐蚀产物膜的研究现状[J]. 腐蚀科学与防护技术,2007,19(2):110-113.
【7】MASLAR J E,HURST W S,BOWERS W J,et al. In situ Raman spectroscopic investigation of aqueous iron corrosion at elevated temperatures and pressures[J]. Journal of the Electrochemical Society,2000,147(7):2532-2542.
【8】KIM J,CHOI K J,CHI B B,et al. In situ Raman spectroscopic analysis of surface oxide films on Ni-base alloy/low alloy steel dissimilar metal weld interfaces in high temperature water[J]. Journal of Nuclear Materials,2014,449(1/3):181-187.
【9】KIM J H,HWANG I S. Development of an in situ Raman spectroscopic system for surface oxide films on metals and alloys in high temperature water[J]. Nuclear Engineering & Design,2014,235(9):1029-1040.
【10】TERACHI T,TOTSUKA N,YAMADA T,et al. Influence of dissolved hydrogen on structure of oxide film on alloy 600 formed in primary water of pressurized water reactors[J]. Journal of Nuclear Science & Technology,2003,40(7):509-516.
【11】SENNOUR M,MARCHETTI L,MARTIN F,et al. A detailed TEM and SEM study of Ni-base alloys oxide scales formed in primary conditions of pressurized water reactor[J]. Journal of Nuclear Materials,2010,402:147-156.
【12】TERACHI T,YAMADA T, TOMOKI M,et al. Corrosion behavior of stainless steels in simulated PWR primary water-effect of chromium content in alloys and dissolved hydrogen[J]. Journal of Nuclear Science & Technology,2008,45(10):975-984.
相关信息
