<strong>FeCrAl</strong>表面氧化对氘渗透性能影响研究

doi:10.11902/1005.4537.2025.123

中国腐蚀与防护学报

2026, Vol. 46

Issue (2): 483-490 CSTR: 32134.14.1005.4537.2025.123 DOI: 10.11902/1005.4537.2025.123

研究报告

本期目录 | 过刊浏览

FeCrAl表面氧化对氘渗透性能影响研究

高士鑫¹^,², 尹春雨¹^,², 巫英伟¹(

), 黄洪涛³, 张坤², 何梁², 叶天舟², 陈平²

^1.西安交通大学动力工程多相流国家重点实验室陕西省先进核能工程研究中心西安 710049
^2.中国核动力研究设计院先进核能技术全国重点实验室成都 610213
^3.中山大学中法核工程与技术学院珠海 519082

Effect of Surface Oxidation on Deuterium Permeation Performance of a Ferritic FeCrAl Alloy at 300-550 ℃

GAO Shixin¹^,², YIN Chunyu¹^,², WU Yingwei¹(

), HUANG Hongtao³, ZHANG Kun², HE Liang², YE Tianzhou², CHEN Ping²

^1.State Key Laboratory of Multiphase Flow in Power Engineering, Shaanxi Engineering Research Center of Advanced Nuclear Energy, Xi'an Jiaotong University, Xi'an 710049, China
^2.Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu 610213, China
^3.Sino-French Institute of Nuclear Energy and Technology, Sun Yat-Sen University, Zhuhai 519082, China

引用本文:

高士鑫, 尹春雨, 巫英伟, 黄洪涛, 张坤, 何梁, 叶天舟, 陈平. FeCrAl表面氧化对氘渗透性能影响研究[J]. 中国腐蚀与防护学报, 2026, 46(2): 483-490.
Shixin GAO, Chunyu YIN, Yingwei WU, Hongtao HUANG, Kun ZHANG, Liang HE, Tianzhou YE, Ping CHEN. Effect of Surface Oxidation on Deuterium Permeation Performance of a Ferritic FeCrAl Alloy at 300-550 ℃[J]. Journal of Chinese Society for Corrosion and protection, 2026, 46(2): 483-490.

全文: PDF(8267 KB) HTML

摘要:

铁素体FeCrAl合金因其优异抗氧化性能，是耐事故燃料(ATF)包壳材料的理想候选。本文通过测量氘在FeCrAl合金中渗透率，研究了氘在FeCrAl合金中的渗透行为，并分析了FeCrAl合金表面纳米氧化膜对氘渗透行为的影响。通过AES、XPS对氘渗透测量后的样品表面氧化膜进行了表征分析，表明氧化膜为Cr₂O₃，Al₂O₃和Fe₂O₃的混合物。测量过程中，450 ℃以下的氧化对氘渗透的影响并不显著，尤其在360 ℃较低温度下，氧元素分布主要集中从表面至深度约150 nm以内；550 ℃时氧化膜厚度增加至500 nm，导致渗透率、扩散系数和溶解度降低，显示出明显的阻氘效应。

关键词 ： FeCrAl合金, 氧化膜, 氘渗透率, 耐事故燃料, 核燃料包壳管

Abstract：

Ferritic FeCrAl alloys have emerged as a highly promising candidate material for accident-tolerant fuel (ATF) claddings due to their outstanding oxidation resistance. In this article, the permeation behavior of deuterium in hot-rolled plate of a FeCrAl alloy Fe-13Cr-4.5Al-2.2Mo-1.1Nb was studied via a home-made set in temperature range of 300-550 ℃ aiming in quantifying the deuterium permeability. Meanwhile, the tested samples were characterized by means of SEM with EDS, AES and XPS in terms of the influence of the in situ formed oxide scale on the deuterium permeation behavior in the alloy. The results revealed that the in situ formed nanometer-thick oxide scale on the alloy surface consisted mainly of Cr₂O₃, Al₂O₃, and Fe₂O₃. Notably, the former oxide scale during the testing process at temperatures below 450 ℃ had negligible influence on the deuterium permeation behavior in FeCrAl alloy. However, during the measurement process at 550 ℃, the in-situ formed oxide scale led to a significant reduction in deuterium permeability, diffusivity, and solubility compared to that at 450 ℃. In terms of the oxygen distribution on the tested sample at 360 ℃, oxygen was mainly concentrated within a depth of approximately 150 nm on the top surface. Conversely, after testing at 550 ℃, oxygen distribution exhibited a deeper and more homogeneous profile, with a maximum penetration depth of around 500 nm. Collectively, the deuterium permeation test results demonstrated that an in-situ formed surface oxide scale with a thickness of approximately 500 nm exerted a pronounced deuterium-barrier effect, providing critical insights into the utilization of FeCrAl alloys for ATF applications.

Key words： FeCrAl alloy oxide film deuterium permeability accident tolerant fuel nuclear fuel cladding

收稿日期: 2025-04-21 32134.14.1005.4537.2025.123

ZTFLH:

TG174

基金资助:国家重点研发计划课题(2020YFB1902103)

通讯作者: 巫英伟，E-mail：wyw810@mail.xjtu.edu.cn，研究方向为聚焦核燃料元件多物理场耦合机理及核反应堆热工安全分析

作者简介: 高士鑫，男，1988年生，高级工程师

	服务

	把本文推荐给朋友
	加入引用管理器
	E-mail Alert
	RSS
	作者相关文章
	高士鑫
	尹春雨
	巫英伟
	黄洪涛
	张坤
	何梁
	叶天舟
	陈平
44.8K

链接本文:

https://www.jcscp.org/CN/10.11902/1005.4537.2025.123 或 https://www.jcscp.org/CN/Y2026/V46/I2/483

图1 氘渗透测试装置[34]

图2 原始FeCrAl合金材料的SEM形貌及EDS元素分布

图3 原始Fe-13Cr-4.5Al-2.2Mo-1.1Nb合金材料的XRD图

图4 原始Fe-13Cr-4.5Al-2.2Mo-1.1Nb合金材料金相组织

图5 全部温度点渗透流量-时间曲线

表1 Fe-13Cr-4.5Al-2.2Mo-1.1Nb合金在不同温度点渗透数据

图6 氘在Fe-13Cr-4.5Al-2.2Mo-1.1Nb合金样品中的渗透率、扩散系数和溶解度

图7 样品氘渗透测试后表面形貌

图8 AES表面原子分数随样品深度变化

图9 360 ℃测试后样品表面元素的XPS价态分析

[1]	Zinkle S J, Terrani K A, Gehin J C, et al. Accident tolerant fuels for LWRs: A perspective [J]. J. Nucl. Mater., 2014, 448: 374
[2]	Rebak R B, Yin L, Andresen P L. Resistance of ferritic FeCrAl alloys to stress corrosion cracking for light water reactor fuel cladding applications [J]. Corrosion, 2020, 76: 1
[3]	Raiman S S, Field K G, Rebak R B, et al. Hydrothermal corrosion of 2nd generation FeCrAl alloys for accident tolerant fuel cladding [J]. J. Nucl. Mater., 2020, 536: 152221
[4]	Terrani K A, Zinkle S J, Snead L L. Advanced oxidation-resistant iron-based alloys for LWR fuel cladding [J]. J. Nucl. Mater., 2014, 448: 420
[5]	Yin L, Jurewicz T B, Larsen M, et al. Uniform corrosion of FeCrAl cladding tubing for accident tolerant fuels in light water reactors [J]. J. Nucl. Mater., 2021, 554: 153090
[6]	Park D J, Kim H G, Park J Y, et al. A study of the oxidation of FeCrAl alloy in pressurized water and high-temperature steam environment [J]. Corros. Sci., 2015, 94: 459
[7]	Rebak R B. Versatile oxide films protect FeCrAl alloys under normal operation and accident conditions in light water power reactors [J]. JOM, 2018, 70: 176
[8]	Parisi C, Ma Z G, Mandelli D, et al. Risk-informed safety analysis for accident tolerant fuels [J]. Nucl. Sci. Eng., 2020, 194: 748
[9]	Massey C P, Terrani K A, Dryepondt S N, et al. Cladding burst behavior of Fe-based alloys under LOCA [J]. J. Nucl. Mater., 2016, 470: 128
[10]	Kane K A, Lee S K, Bell S B, et al. Burst behavior of nuclear grade FeCrAl and Zircaloy-2 fuel cladding under simulated cyclic dryout conditions [J]. J. Nucl. Mater., 2020, 539: 152256
[11]	Robb K R, Howell M, Ott L J. Parametric and experimentally informed BWR severe accident analysis using FeCrAl (M3FT-17OR020205041) [R]. Oak Ridge: ORNL, 2017
[12]	Huang S Y, Dolley E, An K, et al. Microstructure and tensile behavior of powder metallurgy FeCrAl accident tolerant fuel cladding [J]. J. Nucl. Mater., 2022, 560: 153524
[13]	Wang P, Grdanovska S, Bartels D M, et al. Effect of radiation damage and water radiolysis on corrosion of FeCrAl alloys in hydrogenated water [J]. J. Nucl. Mater., 2020, 533: 152108
[14]	Rebak R B, Terrani K A, Gassmann W P, et al. Improving nuclear power plant safety with FeCrAl alloy fuel cladding [J]. MRS Adv., 2017, 2: 1217
[15]	Field K G, Littrell K C, Briggs S A. Precipitation of α′ in neutron irradiated commercial FeCrAl alloys [J]. Scr. Mater., 2018, 142: 41
[16]	Gao S X, Duan Z G, Zhou Y, et al. Preliminary evaluation of FeCrAl-UN fuel rod performance [A]. Proceedings of the Top Fuel 2019 [C]. Seattle, 2019: 637
[17]	Gao S X, Li W J, Chen P, et al. Study on irradiation behavior of fuel rods with FeCrAl cladding [J]. Nucl. Power Eng., 2017, 38(5): 175
[17]	高士鑫, 李文杰, 陈平等. FeCrAl包壳燃料棒辐照行为研究 [J]. 核动力工程, 2017, 38(5): 175
[18]	Tu T, Gao S X, Zhou Y, et al. Simulation analysis of FeCrAl-UN fuel rod performance [J]. Nucl. Power Eng., 2021, 42(S2): 165
[18]	涂腾, 高士鑫, 周毅等. FeCrAl-UN燃料棒性能模拟分析 [J]. 核动力工程, 2021, 42(S2): 165
[19]	Wu W S, Zhang R Q, Ran G, et al. Ion irradiation behavior of a new type of nuclear grade FeCrAl alloy [J]. Trans. Mater. Heat Treat., 2019, 40(6): 88
[19]	吴伟松, 张瑞谦, 冉广等. 一种新型核级FeCrAl合金的离子辐照行为 [J]. 材料热处理学报, 2019, 40(6): 88
[20]	Meng F L, Zhang Q, Liu T, et al. Study on fretting wear performance of four cladding materials for nuclear power [J]. Lubr. Eng., 2021, 46(1): 86
[20]	孟繁良, 张强, 刘彤等. 四种核电用包壳材料的微动磨损性能研究 [J]. 润滑与密封, 2021, 46(1): 86
[21]	Li H, Mei Q L, Fu Y R. Analyses of generation and release of tritium in nuclear power plant [J]. Atom. Energy Sci. Technol., 2015, 49: 739
[21]	黎辉, 梅其良, 付亚茹. 核电厂氚的产生和排放分析 [J]. 原子能科学技术, 2015, 49: 739
[22]	Dwivedi S K, Vishwakarma M. Hydrogen embrittlement in different materials: A review [J]. Int. J. Hydrogen Energy, 2018, 43: 21603
[23]	Hu X X, Terrani K A, Wirth B D, et al. Hydrogen permeation in FeCrAl alloys for LWR cladding application [J]. J. Nucl. Mater., 2015, 461: 282
[24]	Sun X K, Xu J. Permeation of hydrogen in 21-6-9 austenitic stainless steel [J]. J. Chin. Soc. Corros. Prot., 1987, 7: 274
[24]	孙秀魁, 徐坚. 氢在21-6-9奥氏体不锈钢中的渗透 [J]. 中国腐蚀与防护学报, 1987, 7: 274
[25]	Bell J T, Redman J D, Bittner H F. Tritium permeation through clean construction alloys [J]. J. Mater. Energy Syst., 1979, 1: 55
[26]	Forcey K S, Ross D K, Simpson J C B, et al. Hydrogen transport and solubility in 316L and 1.4914 steels for fusion reactor applications [J]. J. Nucl. Mater., 1988, 160: 117
[27]	Shan C Q, Wu A J, Chen Q W. The behavior of diffusion and permeation of tritium through 316L stainless steel [J]. J. Nucl. Mater., 1991, 179-181: 322
[28]	San Marchi C, Somerday B P, Robinson S L. Permeability, solubility and diffusivity of hydrogen isotopes in stainless steels at high gas pressures [J]. Int. J. Hydrogen Energy, 2007, 32: 100
[29]	Hashimoto E, Kino T. Hydrogen permeation through type 316 stainless steels and ferritic steel for a fusion reactor [J]. J. Nucl. Mater., 1985, 133-134: 289
[30]	Sun X K, Xu J, Li Y Y. Hydrogen permeation behaviour in austenitic stainless steels [J]. Mater. Sci. Eng., 1989, 114A: 179
[31]	Jung P. Compositional variation of hydrogen permeability in ferritic alloys and steels [J]. J. Nucl. Mater., 1996, 238: 189
[32]	Georgiev J S, Anestiev L A. Influence of the surface processes on the hydrogen permeation through ferritic steel and amorphous Fe₄₀Ni₄₀Mo₄B₁₆ alloy specimens [J]. J. Nucl. Mater., 1997, 249: 133
[33]	Peñalva I, Alberro G, Aranburu J, et al. Influence of the Cr content on the permeation of hydrogen in Fe alloys [J]. J. Nucl. Mater., 2013, 442: S719
[34]	Gao S X, Duan Z G, Wu Y W, et al. Deuterium permeability and diffusivity in FeCrAl alloys for LWR cladding application [J]. Int. J. Hydrogen Energy, 2022, 47: 20323
[35]	Xu Y P, Zhao S X, Liu F, et al. Studies on oxidation and deuterium permeation behavior of a low temperature α-Al₂O₃-forming Fe-Cr-Al ferritic steel [J]. J. Nucl. Mater., 2016, 477: 257
[36]	Lyu Y M, Xu Y P, Pan X D, et al. Efficient deuterium permeation reduction coating formed by oxidizing the Fe-Cr-Al ferritic steel in reduced oxygen atmosphere at 973 K [J]. J. Nucl. Mater., 2020, 530: 151962
[37]	Garud Y S, Hoffman A K, Rebak R B. Hydrogen isotopes permeation in clean or unoxidized FeCrAl alloys: A review [J]. Metall. Mater. Trans., 2022, 53A: 773
[38]	Sakamoto K, Miura Y, Ukai S, et al. Development of accident tolerant FeCrAl-ODS fuel cladding for BWRs in Japan [J]. J. Nucl. Mater., 2021, 557: 153276
[39]	Zhou X, Wu D K, Cheng X, et al. Research progress of detection techniques for permeated hydrogen [J]. J. Chin. Soc. Corros. Prot., 2023, 43: 1203
[39]	周欣, 吴大康, 成旭等. 渗透氢检测方法研究进展 [J]. 中国腐蚀与防护学报, 2023, 43: 1203
[40]	Han R Z, Jia J W, Li Y, et al. Corrosion behavior of three super austenitic stainless steels in a molten salts mixture at 650-750 ℃ [J]. J. Chin. Soc. Corros. Prot., 2023, 43: 421
[40]	韩瑞珠, 贾建文, 李阳等. 超级奥氏体不锈钢的热腐蚀行为及机理研究 [J]. 中国腐蚀与防护学报, 2023, 43: 421
[41]	Louthan Jr M R, Derrick R G. Hydrogen transport in austenitic stainless steel [J]. Corros. Sci., 1975, 15: 565
[42]	Moulder J F, Stickle W F, Sobol P E, et al. Chastain J, King Jr R C. Handbook of X-Ray Photoelectron Spectroscopy [M]. Eden Prairie: Perkin-Elmer Corporation, 1992: 221
[43]	Mathieu H J, Landolt D. An investigation of thin oxide films thermally grown in situ on Fe 24Cr and Fe 24Cr 11Mo by auger electron spectroscopy and X-ray photoelectron spectroscopy [J]. Corros. Sci., 1986, 26: 547
[44]	Biesinger M C, Payne B P, Grosvenor A P, et al. Resolving surface chemical states in XPS analysis of first row transition metals, oxides and hydroxides: Cr, Mn, Fe, Co and Ni [J]. Appl. Surf. Sci., 2011, 257: 2717
[45]	Pan X D, Xu Y P, Lu T, et al. First-principles study on the dissolution and diffusion properties of hydrogen in α-Al₂O₃ [J]. Ceram. Int., 2021, 47: 5699
[46]	Li N, Parker S S, Wood E S, et al. Oxide morphology of a FeCrAl alloy, Kanthal APMT, following extended aging in air at 300 ℃ to 600 ℃ [J]. Metall. Mater. Trans., 2018, 49A: 2940
[47]	Li N, Parker S S, Saleh T A, et al. Intermediate temperature corrosion behaviour of Fe-12Cr-6Al-2Mo-0.2Si-0.03Y alloy (C26M) at 300-600 ℃ [J]. Corros. Sci., 2019, 157: 274

[1]	张金宇, 李欣, 张磊, 陈志华, 杜雨昕, 冯贺鑫, 张雪, 张洋鹏, 林如山, 李瑛, 戎利建. 几种17Cr系不锈钢在氯化物蒸汽中的腐蚀行为研究[J]. 中国腐蚀与防护学报, 2026, 46(2): 576-582.
[2]	王芬玲, 尚丽梅, 张乃强, 朱忠亮. 超临界水环境中汽轮机阀门材料氧化特性研究[J]. 中国腐蚀与防护学报, 2025, 45(5): 1219-1232.
[3]	蔡科涛, 季磊, 张震, 冯强, 邓伟林, 兰贵红, 何莎, 赵占勇, 白培康. Mg-Gd-Y-Zn-Zr合金在NaCl和Na₂SO₄ 溶液中腐蚀行为研究[J]. 中国腐蚀与防护学报, 2025, 45(5): 1289-1299.
[4]	高云霞, 何琨, 张瑞谦, 梁雪, 王先平, 方前锋. 氧含量对国产FeCrAl基合金长周期腐蚀性能的影响[J]. 中国腐蚀与防护学报, 2025, 45(4): 1081-1088.
[5]	袁小虎, 李定骏, 王天剑, 郭显平, 张乃强, 朱忠亮. 超临界水环境中三种Ni-Cr涂层氧化特性研究[J]. 中国腐蚀与防护学报, 2024, 44(1): 119-129.
[6]	任延杰, 吕云蕾, 戴汀, 郭晓慧, 陈荐, 周立波, 邱玮, 牛焱. 三元Co-Ni-Al合金在800~1000 ℃纯氧中的氧化行为研究[J]. 中国腐蚀与防护学报, 2022, 42(6): 995-1001.
[7]	朱忠亮, 马辰昊, 李宇旸, 肖博, 袁小虎, 王硕, 徐鸿, 张乃强. 镍基合金Inconel617B在700 ℃超临界水环境中的氧化行为研究[J]. 中国腐蚀与防护学报, 2022, 42(4): 655-661.
[8]	陈振宁, 雍兴跃, 陈晓春. 镁合金微弧氧化膜中微缺陷问题研究进展[J]. 中国腐蚀与防护学报, 2022, 42(1): 1-8.
[9]	邵银华, 王金龙, 张伟, 张甲, 李玲, 杜汐然, 陈明辉, 朱圣龙, 王福会. 耐热镁合金Mg-14Gd-2.3Zn-Zr的高温氧化行为研究[J]. 中国腐蚀与防护学报, 2022, 42(1): 73-78.
[10]	王来滨, 刘侠和, 王梅, 高俊杰. 三价铬基转化膜生长动力学研究现状及进展[J]. 中国腐蚀与防护学报, 2021, 41(5): 571-578.
[11]	魏欣欣,张波,马秀良. FeCr₁₅Ni₁₅单晶600 ℃下热生长氧化膜的TEM观察[J]. 中国腐蚀与防护学报, 2019, 39(5): 417-422.
[12]	肖金涛,陈妍,邢明秀,鞠鹏飞,孟引根,王芳. 工艺参数对2195铝锂合金阳极氧化膜的耐蚀性影响[J]. 中国腐蚀与防护学报, 2019, 39(5): 431-438.
[13]	郝利新, 贾瑞灵, 张慧霞, 张伟, 赵婷, 翟熙伟. 7A52铝合金双丝MIG焊接头的不均匀性对其表面微弧氧化膜腐蚀防护作用的影响[J]. 中国腐蚀与防护学报, 2018, 38(3): 219-225.
[14]	杜开发,王彬,甘复兴,汪的华. 铜锡合金阳极在熔融碳酸盐中氧化膜的形成及其防护性能[J]. 中国腐蚀与防护学报, 2017, 37(5): 421-427.
[15]	冯立, 张立功, 李思振, 郑大江, 林昌健, 董士刚. 柠檬酸铁浓度对镁合金微弧氧化黑色膜层微观结构及耐蚀性的影响[J]. 中国腐蚀与防护学报, 2017, 37(4): 360-365.

Viewed

Full text

Abstract

Cited

Shared

Discussed