铁离子辐照对核用304不锈钢在高温水中腐蚀行为的影响
Effect of Iron Irradiation on Corrosion Behaviors of 304 Stainless Steel in High Temperature Water
摘 要
利用3.5 MeV的铁离子对304不锈钢进行模拟辐照，研究了辐照对核电结构材料腐蚀行为的影响，并对材料内部微观结构、平均腐蚀速率、腐蚀产物形貌、结构及成分等进行了表征。结果表明，辐照使材料内部引入大量位错缺陷，增加了材料在高温水环境中的平均腐蚀速率。辐照试样腐蚀后形成的氧化膜更加不均匀，同时氧化膜内Cr含量有所降低。辐照试样中的离子扩散过程加速是导致氧化膜保护性变差，进而腐蚀加速的根本原因。
辐照
缺陷
腐蚀
stainless steel
irradiation
defect
corrosion
Abstract
Using 3.5 MeV iron ions to simulate irradiating 304 stainless steel, the effect of irradiation on the corrosion behavior of nuclear power structure materials was studied. The internal microstructure, average corrosion rate, morphology, structure and composition of corrosion products were characterized. The results showed that irradiation introduced a large number of dislocation defects inside the material, which increased the average corrosion rate of the material in a high-temperature water environment. The oxide film formed after the irradiated sample corroded was more uneven, and the Cr content in the oxide film was reduced. The acceleration of the ion diffusion process in the irradiated sample was the root cause of the deterioration of the protection of the oxide film and the acceleration of corrosion.
中图分类号 TG174 DOI 10.11973/fsyfh-202202002
所属栏目 试验研究
基金项目 国家自然科学基金（51771211）；国家重点研发计划（2016YFE0105200；2017YFB0702100）；中科院前沿科学重点研究计划（QYZDY-SSWJSC012）；中科院重点任务（ZDRW-CN-2017-1）
收稿日期 2020/8/12
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引用该论文: YAN Honglin,ZHANG Zhiming,WANG Jianqiu,HAN Enhou. Effect of Iron Irradiation on Corrosion Behaviors of 304 Stainless Steel in High Temperature Water[J]. Corrosion & Protection, 2022, 43(2): 10
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参考文献
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【32】WANG J Z, WANG J Q, MING H L, et al. Effect of pH on corrosion behavior of 316L stainless steel in hydrogenated high temperature water[J]. Materials and Corrosion, 2018, 69(5):580-589.
【33】KUANG W J, WU X Q, HAN E H, et al. Effect of nickel ion from autoclave material on oxidation behaviour of 304 stainless steel in oxygenated high temperature water[J]. Corrosion Science, 2011, 53(3):1107-1114.
【34】STELLWAG B. The mechanism of oxide film formation on austenitic stainless steels in high temperature water[J]. Corrosion Science, 1998, 40(2/3):337-370.
【35】MACDONALD D D, URQUIDI-MACDONALD M. Theory of steady-state passive films[J]. Journal of the Electrochemical Society, 1990, 137(8):2395-2402.
【36】SEYEUX A, MAURICE V, MARCUS P. Oxide film growth kinetics on metals and alloys[J]. Journal of the Electrochemical Society, 2013, 160(6):C189-C196.
【37】MACDONALD D D. The point defect model for the passive state[J]. Journal of the Electrochemical Society, 1992, 139(12):3434-3449.
【38】YAMAMOTO T, FUSHIMI K, MIURA S, et al. Influence of substrate dislocation on passivation of pure iron in pH 8.4 borate buffer solution[J]. Journal of the Electrochemical Society, 2010, 157(7):C231.
【39】ZHANG Z M, WANG J Q, HAN E H, et al. Influence of later-dissolved oxygen on microstructural changes in oxide films formed on Alloy 690TT in hydrogenated primary water[J]. Corrosion Science, 2015, 94:245-254.
【40】FUKUMURA T, FUKUYA K, FUJII K, et al. Grain boundary oxidation of neutron irradiated stainless steels in simulated PWR water[M]//The Minerals, Metals & Materials Series. Cham:Springer International Publishing, 2017:2153-2163.
【2】ROBERTSON J. The mechanism of high temperature aqueous corrosion of stainless steels[J]. Corrosion Science, 1991, 32(4):443-465.
【3】RAIMAN S S, BARTELS D M, WAS G S. Radiolysis driven changes to oxide stability during irradiation-corrosion of 316L stainless steel in high temperature water[J]. Journal of Nuclear Materials, 2017, 493:40-52.
【4】WAS G S, BUSBY J T. Role of irradiated microstructure and microchemistry in irradiation-assisted stress corrosion cracking[J]. Philosophical Magazine, 2005, 85(4/5/6/7):443-465.
【5】SCOTT P. A review of irradiation assisted stress corrosion cracking[J]. Journal of Nuclear Materials, 1994, 211(2):101-122.
【6】JIAO Z, WAS G S. Localized deformation and IASCC initiation in austenitic stainless steels[J]. Journal of Nuclear Materials, 2008, 382(2/3):203-209.
【7】EDWARDS D J, SIMONEN E P, BRUEMMER S M. Evolution of fine-scale defects in stainless steels neutron-irradiated at 275℃[J]. Journal of Nuclear Materials, 2003, 317(1):13-31.
【8】POKOR C, BRECHET Y, DUBUISSON P, et al. Irradiation damage in 304 and 316 stainless steels:experimental investigation and modeling.Part I:Evolution of the microstructure[J]. Journal of Nuclear Materials, 2004, 326(1):19-29.
【9】ALLEN T R, BUSBY J T, WAS G S, et al. On the mechanism of radiation-induced segregation in austenitic Fe-Cr-Ni alloys[J]. Journal of Nuclear Materials, 1998, 255(1):44-58.
【10】HE M R, JOHNSON D C, WAS G S, et al. The role of grain boundary microchemistry in irradiation-assisted stress corrosion cracking of a Fe-13Cr-15Ni alloy[J]. Acta Materialia, 2017, 138:61-71.
【11】BURNS W G, MOORE P B. Water radiolysis and its effect upon in-reactor zircaloy corrosion[J]. Radiation Effects, 1976, 30(4):233-242.
【12】WAS G S, ASHIDA Y, ANDRESEN P L. Irradiation-assisted stress corrosion cracking[J]. Corrosion Reviews, 2011, 29(1/2):7-49. DOI:10.1515/corrrev.2011.020.
【13】ANDRESEN P L, WAS G S. A historical perspective on understanding IASCC[J]. Journal of Nuclear Materials, 2019, 517:380-392.
【14】ANDRESEN P L. Emerging issues and fundamental processes in environmental cracking in hot water[J]. CORROSION, 2008, 64(5):439-464.
【15】WAS G S, ALEXANDREANU B, BUSBY J. Localized deformation induced IGSCC and IASCC of austenitic alloys in high temperature water[J]. Key Engineering Materials, 2004, 261/262/263:885-902.
【16】MCMURTREY M D, CUI B, ROBERTSON I, et al. Mechanism of dislocation channel-induced irradiation assisted stress corrosion crack initiation in austenitic stainless steel[J]. Current Opinion in Solid State and Materials Science, 2015, 19(5):305-314.
【17】MCMURTREY M D, WAS G S, CUI B, et al. Strain localization at dislocation channel-grain boundary intersections in irradiated stainless steel[J]. International Journal of Plasticity, 2014, 56:219-231.
【18】POKOR C, BRECHET Y, DUBUISSON P, et al. Irradiation damage in 304 and 316 stainless steels:experimental investigation and modeling. Part I:Evolution of the microstructure[J]. Journal of Nuclear Materials, 2004, 326(1):19-29.
【19】BUSBY J T, HASH M C, WAS G S. The relation ship between hardness and yield stress in irradiated austenitic and ferritic steels[J]. Journal of Nuclear Materials, 2005, 336(2/3):267-278.
【20】DENG P, PENG Q J, HAN E H, et al. Effect of irradiation on corrosion of 304 nuclear grade stainless steel in simulated PWR primary water[J]. Corrosion Science, 2017, 127:91-100.
【21】BRUEMMER S M, SIMONEN E P, SCOTT P M, et al. Radiation-induced material changes and susceptibility to intergranular failure of light-water-reactor core internals[J]. Journal of Nuclear Materials, 1999, 274(3):299-314.
【22】WANG P, WAS G S. Oxidation of zircaloy-4 during in situ proton irradiation and corrosion in PWR primary water[J]. Journal of Materials Research, 2015, 30(9):1335-1348.
【23】RAIMAN S S, WAS G S. Accelerated corrosion and oxide dissolution in 316L stainless steel irradiated in situ in high temperature water[J]. Journal of Nuclear Materials, 2017, 493:207-218.
【24】PERRIN S, MARCHETTI L, DUHAMEL C, et al. Influence of irradiation on the oxide film formed on 316 L stainless steel in PWR primary water[J]. Oxidation of Metals, 2013, 80(5/6):623-633.
【25】WAS G S, JIAO Z, GETTO E, et al. Emulation of reactor irradiation damage using ion beams[J]. Scripta Materialia, 2014, 88:33-36.
【26】ZIEGLER J F, ZIEGLER M D, BIERSACK J P. SRIM-The stopping and range of ions in matter (2010)[J]. Nuclear Instruments and Methods in Physics Research Section B:Beam Interactions With Materials and Atoms, 2010, 268(11/12):1818-1823.
【27】LISTER D H, DAVIDSON R D, MCALPINE E. The mechanism and kinetics of corrosion product release from stainless steel in lithiated high temperature water[J]. Corrosion Science, 1987, 27(2):113-140.
【28】ZIEMNIAK S E, HANSON M. Zinc treatment effects on corrosion behavior of 304 stainless steel in high temperature, hydrogenated water[J]. Corrosion Science, 2006, 48(9):2525-2546.
【29】KUANG W J, SONG M, WAS G S. Insights into the stress corrosion cracking of solution annealed alloy 690 in simulated pressurized water reactor primary water under dynamic straining[J]. Acta Materialia, 2018, 151:321-333.
【30】韩恩厚, 王俭秋, 吴欣强, 等. 核电高温高压水中不锈钢和镍基合金的腐蚀机制[J]. 金属学报, 2010, 46(11):1379-1390.
【31】TERACHI T, YAMADA T, MIYAMOTO T, 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 and Technology, 2008, 45(10):975-984.
【32】WANG J Z, WANG J Q, MING H L, et al. Effect of pH on corrosion behavior of 316L stainless steel in hydrogenated high temperature water[J]. Materials and Corrosion, 2018, 69(5):580-589.
【33】KUANG W J, WU X Q, HAN E H, et al. Effect of nickel ion from autoclave material on oxidation behaviour of 304 stainless steel in oxygenated high temperature water[J]. Corrosion Science, 2011, 53(3):1107-1114.
【34】STELLWAG B. The mechanism of oxide film formation on austenitic stainless steels in high temperature water[J]. Corrosion Science, 1998, 40(2/3):337-370.
【35】MACDONALD D D, URQUIDI-MACDONALD M. Theory of steady-state passive films[J]. Journal of the Electrochemical Society, 1990, 137(8):2395-2402.
【36】SEYEUX A, MAURICE V, MARCUS P. Oxide film growth kinetics on metals and alloys[J]. Journal of the Electrochemical Society, 2013, 160(6):C189-C196.
【37】MACDONALD D D. The point defect model for the passive state[J]. Journal of the Electrochemical Society, 1992, 139(12):3434-3449.
【38】YAMAMOTO T, FUSHIMI K, MIURA S, et al. Influence of substrate dislocation on passivation of pure iron in pH 8.4 borate buffer solution[J]. Journal of the Electrochemical Society, 2010, 157(7):C231.
【39】ZHANG Z M, WANG J Q, HAN E H, et al. Influence of later-dissolved oxygen on microstructural changes in oxide films formed on Alloy 690TT in hydrogenated primary water[J]. Corrosion Science, 2015, 94:245-254.
【40】FUKUMURA T, FUKUYA K, FUJII K, et al. Grain boundary oxidation of neutron irradiated stainless steels in simulated PWR water[M]//The Minerals, Metals & Materials Series. Cham:Springer International Publishing, 2017:2153-2163.
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