Effect of Surface Roughness on Corrosion Behavior of 800H Alloy in Supercritical Water Environment
摘 要
通过扫描电镜(SEM)、能谱仪(EDS)和电子背散射衍射(EBSD),研究了表面粗糙度对800H合金在650℃、25 MPa的超临界水环境中均匀腐蚀行为的影响。结果表明:粗磨试样的腐蚀质量增加速率显著低于机械抛光试样的;浸泡1 000 h后,机械抛光试样的腐蚀质量增加是粗磨试样的20倍。振动抛光试样表面生成外层富铁、内层富铬的双层氧化膜,粗磨试样表面生成单层富铬氧化膜,且在氧化膜下方出现明显的富铬滑移带。
Abstract
The effect of surface roughness on general corrosion behavior of 800H alloy in supercritical water environment at 650℃ and 25 MPa was studied by scanning electron microscopy (SEM), energy dispersive spectroscopy (EDS) and electron backscattering diffraction (EBSD). The results showed that the corrosion mass increase rate of rough grinding sample was significantly lower than that of mechanical polishing sample. After immersion for 1 000 h, the corrosion mass of mechanical polishing sample increased 20 times as much as that of rough grounding sample. A double-layer oxide film rich in iron and chromium was formed on the surface of vibration polishing sample, and a single-layer oxide film rich in chromium was formed on the surface of rough grounding sample, and obvious chromium-rich slip band appeared under the oxide film.
中图分类号 TG174 DOI 10.11973/fsyfh-202112001
所属栏目 试验研究
基金项目 国家重点研发计划(2018YFE0116200)
收稿日期 2020/2/20
修改稿日期
网络出版日期
作者单位点击查看
引用该论文: WANG Peng,LIU Zhu,SU Haozhan,GUO Xianglong,CHEN Kai,MA Wujiang,ZHANG Lefu. Effect of Surface Roughness on Corrosion Behavior of 800H Alloy in Supercritical Water Environment[J]. Corrosion & Protection, 2021, 42(12): 1
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】WAS G S,AMPORNRAT P,GUPTA G,et al. Corrosion and stress corrosion cracking in supercritical water[J]. Journal of Nuclear Materials,2007,371(1/2/3):176-201.
【2】张宏亮,罗英,李翔,等. CSR1000结构总体设计方案[J]. 核动力工程,2013,34(1):52-56.
【3】王连杰,卢迪,陈炳德,等. 超临界水堆CSR1000堆芯设计优化[J]. 核动力工程,2016,37(5):161-166.
【4】ZHANG L F,BAO Y C,TANG R. Selection and corrosion evaluation tests of candidate SCWR fuel cladding materials[J]. Nuclear Engineering and Design,2012,249:180-187.
【5】胡梦,沈朝,张乐福. 304NG奥氏体不锈钢在超临界水环境中的腐蚀行为[J]. 腐蚀与防护,2016,37(7):565-571.
【6】沈朝,吴恋恋,张乐福,等. 镍基合金800H的腐蚀性能研究[J]. 腐蚀科学与防护技术,2014,26(2):113-118.
【7】高文华,沈朝,张乐福. HR3C在超临界水中的腐蚀性能研究[J]. 原子能科学技术,2016,50(2):317-322.
【8】GUO X L,CHEN K,GAO W H,et al. A research on the corrosion and stress corrosion cracking susceptibility of 316L stainless steel exposed to supercritical water[J]. Corrosion Science,2017,127:157-167.
【9】沈朝,杜东海,孙耀,等. 镍基合金825在超临界水中的腐蚀性能研究[J]. 原子能科学技术,2014,48(9):1660-1665.
【10】TAN L,REN X,SRIDHARAN K,et al. Effect of shot-peening on the oxidation of alloy 800H exposed to supercritical water and cyclic oxidation[J]. Corrosion Science,2008,50(7):2040-2046.
【11】SHEN Z,WU L,ZHANG L,et al. Corrosion behavior of nickel base alloy 800H in high-temperature and high-pressured water[J]. Corrosion Science and Protection Technology,2014,26:113-118.
【12】CHOUDHRY K I,MAHBOUBI S,BOTTON G A,et al. Corrosion of engineering materials in a supercritical water cooled reactor:characterization of oxide scales on Alloy 800H and stainless steel 316[J]. Corrosion Science,2015,100:222-230.
【13】CHOUDHRY K I,GUZONAS D A,KALLIKRAGAS D T,et al. On-line monitoring of oxide formation and dissolution on alloy 800H in supercritical water[J]. Corrosion Science,2016,111:574-582.
【14】TAN L,SRIDHARAN K,ALLEN T R. The effect of grain boundary engineering on the oxidation behavior of INCOLOY alloy 800H in supercritical water[J]. Journal of Nuclear Materials,2006,348(3):263-271.
【15】PAYET M,MARCHETTI L,TABARANT M,et al. Corrosion mechanisms of 316L stainless steel in supercritical water:the significant effect of work hardening induced by surface finishes[J]. Corrosion Science,2019,157:157-166.
【16】GAO W H,GUO X L,SHEN Z,et al. Corrosion behavior of oxide dispersion strengthened ferritic steels in supercritical water[J]. Journal of Nuclear Materials,2017,486:1-10.
【17】李美栓. 金属的高温腐蚀[M]. 北京:冶金工业出版社,2001.
【18】沈朝,汪家梅,张乐福. 铁素体/马氏体钢和奥氏体不锈钢在超临界水中的腐蚀行为[J]. 上海交通大学学报,2015,49(12):1768-1777.
【19】沈朝,段振刚,孙耀,等. 12Cr-F/M钢在超临界水中的腐蚀行为[J]. 腐蚀与防护,2014,35(5):434-437.
【20】SUN M C,WU X Q,ZHANG Z E,et al. Oxidation of 316 stainless steel in supercritical water[J]. Corrosion Science,2009,51(5):1069-1072.
【21】ATKINSON A. Transport processes during the growth of oxide films at elevated temperature[J]. Reviews of Modern Physics,1985,57(2):437-470.
【22】BEHNAMIAN Y,MOSTAFAEI A,KOHANDEHGHAN A,et al. Characterization of oxide scales grown on alloy 310S stainless steel after long term exposure to supercritical water at 500℃[J]. Materials Characterization,2016,120:273-284.
【23】WRIGHT I G,DOOLEY R B. A review of the oxidation behaviour of structural alloys in steam[J]. International Materials Reviews,2010,55(3):129-167.
【24】石艳柯,张克实. 铜单晶拉伸试样表面滑移带痕迹的晶体塑性分析[J]. 固体力学学报,2011,32(6):557-565.
【25】CHANG L T,BURKE M G,SCENINI F. Understanding the effect of surface finish on stress corrosion crack initiation in warm-forged stainless steel 304L in high-temperature water[J]. Scripta Materialia,2019,164:1-5.
【26】BEHNAMIAN Y,MOSTAFAEI A,KOHANDEHGHAN A,et al. Internal oxidation and crack susceptibility of alloy 310S stainless steel after long term exposure to supercritical water at 500℃[J]. The Journal of Supercritical Fluids,2017,120:161-172.
【27】HALVARSSON M,TANG J E,ASTEMAN H,et al. Microstructural investigation of the breakdown of the protective oxide scale on a 304 steel in the presence of oxygen and water vapour at 600℃[J]. Corrosion Science,2006,48(8):2014-2035.
【28】OTSUKA N,SHIDA Y,FUJIKAWA H. Internal-external transition for the oxidation of Fe-Cr-Ni austenitic stainless steels in steam[J]. Oxidation of Metals,1989,32(1/2):13-45.
【29】GHENO T,JOMARD F,DESGRANGES C,et al. Grain boundary diffusion of chromium in polycrystalline nickel studied by SIMS[J]. Materialia,2019,6:100283.
【30】LOBNIG R E,SCHMIDT H P,HENNESEN K,et al. Diffusion of cations in chromia layers grown on iron-base alloys[J]. Oxidation of Metals,1992,37(1/2):81-93.
【2】张宏亮,罗英,李翔,等. CSR1000结构总体设计方案[J]. 核动力工程,2013,34(1):52-56.
【3】王连杰,卢迪,陈炳德,等. 超临界水堆CSR1000堆芯设计优化[J]. 核动力工程,2016,37(5):161-166.
【4】ZHANG L F,BAO Y C,TANG R. Selection and corrosion evaluation tests of candidate SCWR fuel cladding materials[J]. Nuclear Engineering and Design,2012,249:180-187.
【5】胡梦,沈朝,张乐福. 304NG奥氏体不锈钢在超临界水环境中的腐蚀行为[J]. 腐蚀与防护,2016,37(7):565-571.
【6】沈朝,吴恋恋,张乐福,等. 镍基合金800H的腐蚀性能研究[J]. 腐蚀科学与防护技术,2014,26(2):113-118.
【7】高文华,沈朝,张乐福. HR3C在超临界水中的腐蚀性能研究[J]. 原子能科学技术,2016,50(2):317-322.
【8】GUO X L,CHEN K,GAO W H,et al. A research on the corrosion and stress corrosion cracking susceptibility of 316L stainless steel exposed to supercritical water[J]. Corrosion Science,2017,127:157-167.
【9】沈朝,杜东海,孙耀,等. 镍基合金825在超临界水中的腐蚀性能研究[J]. 原子能科学技术,2014,48(9):1660-1665.
【10】TAN L,REN X,SRIDHARAN K,et al. Effect of shot-peening on the oxidation of alloy 800H exposed to supercritical water and cyclic oxidation[J]. Corrosion Science,2008,50(7):2040-2046.
【11】SHEN Z,WU L,ZHANG L,et al. Corrosion behavior of nickel base alloy 800H in high-temperature and high-pressured water[J]. Corrosion Science and Protection Technology,2014,26:113-118.
【12】CHOUDHRY K I,MAHBOUBI S,BOTTON G A,et al. Corrosion of engineering materials in a supercritical water cooled reactor:characterization of oxide scales on Alloy 800H and stainless steel 316[J]. Corrosion Science,2015,100:222-230.
【13】CHOUDHRY K I,GUZONAS D A,KALLIKRAGAS D T,et al. On-line monitoring of oxide formation and dissolution on alloy 800H in supercritical water[J]. Corrosion Science,2016,111:574-582.
【14】TAN L,SRIDHARAN K,ALLEN T R. The effect of grain boundary engineering on the oxidation behavior of INCOLOY alloy 800H in supercritical water[J]. Journal of Nuclear Materials,2006,348(3):263-271.
【15】PAYET M,MARCHETTI L,TABARANT M,et al. Corrosion mechanisms of 316L stainless steel in supercritical water:the significant effect of work hardening induced by surface finishes[J]. Corrosion Science,2019,157:157-166.
【16】GAO W H,GUO X L,SHEN Z,et al. Corrosion behavior of oxide dispersion strengthened ferritic steels in supercritical water[J]. Journal of Nuclear Materials,2017,486:1-10.
【17】李美栓. 金属的高温腐蚀[M]. 北京:冶金工业出版社,2001.
【18】沈朝,汪家梅,张乐福. 铁素体/马氏体钢和奥氏体不锈钢在超临界水中的腐蚀行为[J]. 上海交通大学学报,2015,49(12):1768-1777.
【19】沈朝,段振刚,孙耀,等. 12Cr-F/M钢在超临界水中的腐蚀行为[J]. 腐蚀与防护,2014,35(5):434-437.
【20】SUN M C,WU X Q,ZHANG Z E,et al. Oxidation of 316 stainless steel in supercritical water[J]. Corrosion Science,2009,51(5):1069-1072.
【21】ATKINSON A. Transport processes during the growth of oxide films at elevated temperature[J]. Reviews of Modern Physics,1985,57(2):437-470.
【22】BEHNAMIAN Y,MOSTAFAEI A,KOHANDEHGHAN A,et al. Characterization of oxide scales grown on alloy 310S stainless steel after long term exposure to supercritical water at 500℃[J]. Materials Characterization,2016,120:273-284.
【23】WRIGHT I G,DOOLEY R B. A review of the oxidation behaviour of structural alloys in steam[J]. International Materials Reviews,2010,55(3):129-167.
【24】石艳柯,张克实. 铜单晶拉伸试样表面滑移带痕迹的晶体塑性分析[J]. 固体力学学报,2011,32(6):557-565.
【25】CHANG L T,BURKE M G,SCENINI F. Understanding the effect of surface finish on stress corrosion crack initiation in warm-forged stainless steel 304L in high-temperature water[J]. Scripta Materialia,2019,164:1-5.
【26】BEHNAMIAN Y,MOSTAFAEI A,KOHANDEHGHAN A,et al. Internal oxidation and crack susceptibility of alloy 310S stainless steel after long term exposure to supercritical water at 500℃[J]. The Journal of Supercritical Fluids,2017,120:161-172.
【27】HALVARSSON M,TANG J E,ASTEMAN H,et al. Microstructural investigation of the breakdown of the protective oxide scale on a 304 steel in the presence of oxygen and water vapour at 600℃[J]. Corrosion Science,2006,48(8):2014-2035.
【28】OTSUKA N,SHIDA Y,FUJIKAWA H. Internal-external transition for the oxidation of Fe-Cr-Ni austenitic stainless steels in steam[J]. Oxidation of Metals,1989,32(1/2):13-45.
【29】GHENO T,JOMARD F,DESGRANGES C,et al. Grain boundary diffusion of chromium in polycrystalline nickel studied by SIMS[J]. Materialia,2019,6:100283.
【30】LOBNIG R E,SCHMIDT H P,HENNESEN K,et al. Diffusion of cations in chromia layers grown on iron-base alloys[J]. Oxidation of Metals,1992,37(1/2):81-93.
相关信息