Please wait a minute...
金属学报  2026, Vol. 62 Issue (8): 1331-1346    DOI: 10.11900/0412.1961.2025.00407
  综述 本期目录 | 过刊浏览 |
熔盐堆用镍基合金失效机理与改性策略研究进展
王优1,2, 陈向阳1,2(), 王煦嘉1(), 汤春桃1, 沈朝3(), 曾小勤3
1 上海核工程研究设计院股份有限公司 上海 200233
2 上海核工程研究设计院股份有限公司 核电关键材料全国重点实验室 上海 200233
3 上海交通大学 材料科学与工程学院 上海 200240
Progress in Failure Mechanisms and Modification Strategies of Nickel-Based Alloys for Molten Salt Reactors
WANG You1,2, CHEN Xiangyang1,2(), WANG Xujia1(), TANG Chuntao1, SHEN Zhao3(), ZENG Xiaoqin3
1 Shanghai Nuclear Engineering Research & Design Institute Co. Ltd. , Shanghai 200233, China
2 Stage Key Laboratory of Materials for Advanced Nuclear Energy, Shanghai Nuclear Engineering Research & Design Institute Co. Ltd. , Shanghai 200233, China
3 School of Materials Science and Engineering, Shanghai Jiao Tong University, Shanghai 200240, China
引用本文:

王优, 陈向阳, 王煦嘉, 汤春桃, 沈朝, 曾小勤. 熔盐堆用镍基合金失效机理与改性策略研究进展[J]. 金属学报, 2026, 62(8): 1331-1346.
You WANG, Xiangyang CHEN, Xujia WANG, Chuntao TANG, Zhao SHEN, Xiaoqin ZENG. Progress in Failure Mechanisms and Modification Strategies of Nickel-Based Alloys for Molten Salt Reactors[J]. Acta Metall Sin, 2026, 62(8): 1331-1346.

全文: PDF(3918 KB)   HTML
摘要: 

熔盐堆作为第四代核能系统的重要堆型,其高温、强腐蚀和辐照耦合环境对结构材料的化学稳定性与服役可靠性提出严苛要求。镍基合金因具有高温相稳定性和低化学活性而成为关键候选材料,但仍面临选择性腐蚀溶解、碲致腐蚀开裂以及辐照加速腐蚀等一系列失效问题。本文系统综述了熔盐堆用镍基合金的多场耦合失效机理,并总结了“成分优化-第二相调控-晶界调控-涂层防护”四维协同改性体系。通过降低Cr含量、优化Mo / W比例抑制溶解;利用氧化物弥散强化颗粒俘获缺陷、阻断扩散;采用晶界工程(GBE)提高低Σ晶界比例,抑制Te渗透;并以Ni-W或SiC涂层形成终端屏障。最后指出,未来应发展原位表征、智能设计与环境自适应技术,实现镍基合金在熔盐堆中的长寿命服役。

关键词 : 镍基合金,  熔盐堆,  失效机理,  改性策略    
Abstract:

The molten salt reactor (MSR) is an important reactor type in Generation IV nuclear systems. However, the high-temperature, corrosive, and irradiation-coupled environment of MSRs compromises the chemical stability and service reliability of structural materials. Nickel-based alloys, featuring an fcc matrix with high thermal stability and low chemical activity, are promising candidates but remain susceptible to selective corrosion dissolution, Te-induced corrosion cracking, and irradiation-accelerated corrosion. This review summarizes the multifield-coupled failure mechanisms of Ni-based alloys for MSRs and outlines a four-dimensional modification framework of “composition optimization, secondary phase regulation, grain boundary regulation, and coating protection”. Lowering the Cr content and optimizing the Mo / W ratios collectively suppress selective dissolution; secondary phase/oxide dispersion strengthened particles trap defects and block diffusion; grain boundary engineering suppresses Te penetration by increasing the fraction of low-Σ boundaries; Ni-W or silicon carbide coatings provide terminal protection. Future efforts should focus on in situ multifield characterization, machine learning-based design, and environment-adaptive regulation of Ni-based alloys to achieve their long-term reliability and engineering application in MSRs.

Key words: nickel-based alloy    molten salt reactor    failure mechanism    modification strategy
收稿日期: 2025-12-10     
ZTFLH:  TG146.1  
基金资助:国家自然科学基金项目(U25B20113);国家自然科学基金项目(52471043);中国科协青年托举人才工程项目(TESS20240818);上海市启明星扬帆专项项目(24YF2718700)
通讯作者: 陈向阳,chenxiangyang3@snerdi.com.cn,主要从事核燃料材料设计研发研究; 王煦嘉,wangxj@snerdi.com.cn,主要从事核反应堆型号研发研究; 沈 朝,shenzhao081@sjtu.edu.cn,主要从事核材料高温腐蚀与防护研究
Corresponding author: CHEN Xiangyang, senior engineer, Tel: (021)61863529, E-mail: chenxiangyang3@snerdi.com.cn; WANG Xujia, professorate senior engineer, Tel: (021)61860728, E-mail: wangxj@snerdi.com.cn; SHEN Zhao, associate professor, Tel: (021)54740838, E-mail: shenzhao081@sjtu.edu.cn
作者简介: 王 优,女,1997年生,工程师,博士
ElementReactionReaction productΔG / (kJ·mol-1)
MoMo + 3HF(l) = MoF3 + 1.5H2(g)MoF3-27.288
NiNi + 2HF(l) = NiF2 + H2(g)NiF2-64.334
FeFe + 3HF(l) = FeF3 + 1.5H2(g)FeF3-127.298
Fe + 2HF(l) = FeF2 + H2(g)FeF2-131.981
CrCr + 2HF(l) = CrF2 + H2(g)CrF2-211.982
Cr + 3HF(l) = CrF3 + 1.5H2(g)CrF3-277.105
MnMn + 2HF(l) = MnF2 + H2(g)MnF2-279.745
NbNb + 5HF(l) = NbF5 + 2.5H2(g)NbF5-377.160
表1  常见活性元素与熔盐组分的化学反应及700 ℃下反应的Gibbs自由能变化(ΔG)汇总[10]
图1  常见氟化物生成反应的ΔG顺序图[11~13]
图2  Ni80Cr20、800H和GH3535合金在熔融FLiNaK盐中腐蚀后的表面和截面形貌及元素分布[14,15]
图3  625合金在700 ℃含0.5%Te的熔融FLiNaK盐中腐蚀48 h后的BSE像及元素线扫描分布曲线[23];Ni在含Te熔融盐中腐蚀后Te沿晶界向基体内部扩散的EPMA像和元素分布图[24];GH3535合金在700 ℃含Te的熔融FLiNaK盐中腐蚀1000 h后的截面形貌及EPMA元素面扫描分布图[26];含Te熔盐腐蚀前后304不锈钢[27]、GH3535合金[24]的室温拉伸曲线图及形貌
Element and phaseReactionΔG
Cr3Te + 2Cr = Cr2Te3-294.60
Cr carbide10.5Te + Cr7C3 = 3.5Cr2Te3 + 3C-840.76
34.5Te + Cr23C6 = 11.5Cr2Te3 + 6C-2997.65
Ni3Te + 2Ni = Ni2Te3-112.96
Ni carbide4.5Te + Ni3C = 1.5Ni2Te3 + C-222.74
Fe2Te + Fe = FeTe2-33.45
Mo2Te + Mo = MoTe2-57.17
4Te + 3Mo = Mo3Te4-123.65
Mo carbide2Te + MoC = MoTe2 + C-27.38
4Te + Mo2C = 2MoTe2 + C-59.68
6Te + Mo3C2 = 3MoTe2 + 2C-96.22
表2  常见合金元素及其碳化物与Te发生化学反应的ΔG汇总[26] (kJ·mol-1)
图4  316L不锈钢在应力状态下的腐蚀开裂行为及应力腐蚀开裂机理示意图[31](a) cross-sectional morphologies of stress-free sample and creep sample after corrosion in molten salt at 565 oC for 830 and 1068 h(b1, b2) comparisons of thickness of corrosion layer (b1) and corrosion rate (b2) between stress-free sample and creep sample after corrosion in molten salt at 565 oC(c) schematics of stress corrosion cracking mechanism (GB—grain boundary)
图5  辐照耦合效应对材料老化的影响[36,38](a) microstructure change[36](b) GB change[38](c) induced segregation and carbide precipitation[38](d) accelerated dissolution corrosion[36]
MaterialT / oCt / hIrradiation conditionh / μm
Hastelloy N700300040.0
1 × 1015 n·cm-247.5
5 × 1015 n·cm-252.4
1 × 1016 n·cm-264.9
Hastelloy N700500023.9
1 × 1015 n·cm-233.9
1 × 1016 n·cm-242.9
5 × 1016 n·cm-254.8
GH35357005000.5
5 × 1016 n·cm-23.0
1.3 × 1017 n·cm-26.7
Inconel 61770050030.0
5 × 1016 n·cm-245.8
1.3 × 1017 n·cm-250.1
Incoloy 800H650407.7
9.64 × 10-4 dpa12.9
Incoloy 800H6508016.2
1.93 × 10-3 dpa17.4
Inconel 600650806.4
2.02 × 10-3 dpa6.3
Inconel 6006501608.6
4.04 × 10-3 dpa9.7
316L650103.9
2.34 × 10-4 dpa6.3
316L6508016.2
1.88 × 10-3 dpa22.8
表3  在辐照耦合效应下常见合金熔盐腐蚀深度汇总[39,41~46]

Alloy

Mass fraction

of Cr / %

Corrosion rate

mm·a-1

Mass loss

mg·cm-2

Haynes 23022.51.0051.5
Inconel 61722.10.6229.5
Hastelloy X21.30.2812.5
Incoloy 800H20.40.6328.0
Hastelloy N6.30.052.5
表4  常见镍基合金在850 ℃熔融FLiNaK盐中腐蚀500 h的腐蚀速率和单位面积失重[49]
图6  第二相/基体界面对材料耐腐蚀、抗辐照性能的作用机制[60,62,64]
图7  晶界工程(GBE)调控前后样品晶界变化[25],不同晶界上二次碳化物的析出形貌[25],及GBE调控后GH3535合金的腐蚀失重及力学性能变化[70]
Typical coating material systemCoating preparation methodMain process feature and applicable condition
Cr, Cr-Zr, Cr-Nb, Cr-AlPhysical vapor deposition (PVD)Forms dense and uniform coatings with controllable thickness; suitable for complex geometries; limited deposition rate; coating adhesion depends on substrate pretreatment
Cr, Cr-Al, Cr-Ni, Cr-FeHigh power impulse magnetron sputtering (HiPIMS)Produces dense, defect-free coatings with high ionization of sputtered species; excellent adhesion and microstructure uniformity; suitable for oxidation- and corrosion-resistant coatings on structural materials

Cr3C2, SiC, TiN

Chemical vapor deposition (CVD)Enables good conformal coverage and high coating purity; applicable for diffusion barriers and high-temperature environments; requires high deposition temperature (700-1000 oC)

Ni, Ni-W, Ni-Mo

Electroplating/electrochemical depositionLow-cost and scalable process; capable of producing uniform metallic coatings; limited by substrate conductivity and coating compactness; post-deposition annealing improves adhesion
Ni, Ni-Cr, Ni-Al, Fe-Cr-AlCold spraySolid-state deposition with minimal oxidation; produces thick coatings with high bonding strength; suitable for large components and localized repair
Ni-Cr, Ni-Cr-Al, Ni-MoLaser cladding/surface meltingAchieves metallurgical bonding with substrate and gradient composition transition; effective for high-temperature oxidation protection; potential thermal stress and dilution at interface

Al2O3, SiO2, Y2O3

Sol-gel/dip coating

Simple and cost-effective; applicable to complex geometries; suitable for oxide protective films; poor adhesion under thermal cycling unless combined with interlayer
表5  常见涂层体系、制备工艺及主要工艺特点与适用条件[71~75]
图8  熔盐堆用镍基合金改性技术路线图
[1] Saint-Germain L S. Technology road-map update for generation IV nuclear energy systems [A]. Generation IV International Forum—GIF [C]. Issy-Les-Moulineaux: Nuclear Energy Agency of the OECD, 2014: 66
[2] LeBlanc D. Molten salt reactors: A new beginning for an old idea [J]. Nucl. Eng. Des., 2010, 240: 1644
[3] Revol J P, Bourquin M, Kadi Y, et al. Thorium Energy for the World [M]. Cham: Springer, 2016: 187
[4] Mathieu L, Heuer D, Brissot R, et al. The thorium molten salt reactor: Moving on from the MSBR [J]. Prog. Nucl. Energy, 2006, 48: 664
[5] Qiu S Z, Zhang D L, Su G H, et al. Research on inherent safety and relative key issues of a molten salt reactor [J]. Atom. Energy Sci. Technol., 2009, 43(suppl.1): 64
[5] 秋穗正, 张大林, 苏光辉 等. 新概念熔盐堆的固有安全性及相关关键问题研究 [J]. 原子能科学技术, 2009, 43(): 64
[6] Wu X Q, Tan J B, Zhang Z Y, et al. Research advance on corrosion fatigue behavior of metallic materials in high-temperature pressurized water, liquid Pb-Bi, and marine environments [J]. Acta Metall. Sin., 2026, 62: 822
[6] 吴欣强, 谭季波, 张兹瑜 等. 金属材料在高温高压水、液态Pb-Bi和海洋环境中的腐蚀疲劳行为研究进展[J]. 金属学报, 2026, 62: 822
[7] Ouyang F Y, Chang C H, Kai J J. Long-term corrosion behaviors of Hastelloy-N and Hastelloy-B3 in moisture-containing molten FLiNaK salt environments [J]. J. Nucl. Mater., 2014, 446: 81
[8] Rowcliffe A F, Mansur L K, Hoelzer D T, et al. Perspectives on radiation effects in nickel-base alloys for applications in advanced reactors [J]. J. Nucl. Mater., 2009, 392: 341
[9] Zhou W Y, Yang Y, Zheng G Q, et al. Proton irradiation-decelerated intergranular corrosion of Ni-Cr alloys in molten salt [J]. Nat. Commun., 2020, 11: 3430
[10] Zheng X W, Jiang L, Wang K, et al. Corrosion and Te embrittlement behaviors of Ni-Mo-Cr-Nb alloy in Te-containing molten salts [J]. J. Nucl. Mater., 2025, 603: 155450
[11] Ding X B. Investigation on the corrosion behavior of Hastelloy N and 316L stainless steel in LiF-NaF-KF molten salt [D]. Shanghai: Shanghai Institute of Applied Physics, 2015
[11] 丁祥彬. Hastelloy N合金和316L不锈钢在LiF-NaF-KF熔盐中的腐蚀行为研究 [D]. 上海: 中国科学院研究生院(上海应用物理研究所), 2015
[12] Forsberg C. Reactors with molten salts: Options and missions [R]. Cadarache: Frederic Joliot & Otto Han Summer School on Nuclear Reactors, 2004
[13] Cihlář M, Mareček M, Uhlíř J, et al. Corrosion of structural materials in NaF-NaBF4 molten salt [J]. Ann. Nucl. Energy, 2025, 211: 111018
[14] Mills S H, Hayes R D, Bieberdorf N, et al. Elucidating the role of Cr migration in Ni-Cr exposed to molten FLiNaK via multiscale characterization [J]. Acta Mater., 2024, 279: 120206
[15] Dai Q L, Ye X X, Ai H, et al. Corrosion of Incoloy 800H alloys with nickel cladding in FLiNaK salts at 850 oC [J]. Corros. Sci., 2018, 133: 349
[16] Zhu H M, Li B C, Zhu J Y, et al. Research progress on corrosion of Ni-based alloy in molten fluorine salt of molten salt reactor [J]. Mater. Rep., 2019, 33: 1813
[16] 朱红梅, 李柏春, 朱锦云 等. 熔盐堆用镍基合金在熔融氟盐中的腐蚀研究进展 [J]. 材料导报, 2019, 33: 1813
[17] Yu Z D, Wu J P, Liu H L, et al. Corrosion behavior of the GH3535 and C276 alloys at the liquid/gas LiCl-KCl salt interface at 550 oC [J]. J. Mater. Eng. Perform., 2025, 34: 13391
[18] Danon A E, Muránsky O, Karatchevtseva I, et al. Molten salt corrosion (FLiNaK) of a Ni-Mo-Cr alloy and its welds for application in energy-generation and energy-storage systems [J]. Corros. Sci., 2020, 164: 108306
[19] McCoy H E, McNabb B. Intergranular cracking of INOR-8 in the MSRE [R]. Oak Ridge: Oak Ridge National Laboratory, 1972
[20] Compere E L, Kirslis S S, Bohlmann E G, et al. Fission product behavior in the molten salt reactor experiment [R]. Oak Ridge: Oak Ridge National Laboratory, 1975
[21] Serp J, Allibert M, Beneš O, et al. The molten salt reactor (MSR) in generation IV: Overview and perspectives [J]. Prog. Nucl. Energy, 2014, 77: 308
[22] Keiser J R. Status of tellurium-Hastelloy N studies in molten fluoride salts [R]. Oak Ridge: Oak Ridge National Laboratory, 1977
[23] Hong M, Chan H L, Scully J R, et al. Corrosion property of Alloy 625 in molten FLiNaK salt according to the tellurium concentrations [J]. J. Nucl. Mater., 2023, 584: 154548
[24] Jiang L, Yu K, Liang J P, et al. Simulation experiment for tellurium-induced intergranular cracking in oxidizing molten salt environment [J]. Corros. Sci., 2023, 225: 111582
[25] Bai Q, Liu B Y, Xia S, et al. Effect of grain boundary engineering on resistance to intergranular corrosion of Hastelloy N alloy after aging [J]. Shanghai Met., 2020, 42(1): 28
[25] 白 琴, 刘冰玉, 夏 爽 等. 晶界工程处理对Hastelloy N合金时效后耐晶间腐蚀性能的影响 [J]. 上海金属, 2020, 42(1): 28
[26] Hu M M, Yang X M, Wang X D, et al. Effect of Te on the corrosion behavior of GH3535 alloy in molten LiF-NaF-KF salt [J]. Corros. Sci., 2024, 227: 111761
[27] Hong M, Chan H L, Xie Y J, et al. Effect of tellurium concentration on the corrosion and mechanical properties of 304 stainless steel in molten FLiNaK salt [J]. Corros. Sci., 2023, 212: 110913
[28] Li X L, Chang L T, Liang W J, et al. Creep deformation and fracture of Ni-based alloy GH3535 in molten FLiNaK and Ar environment [J]. Corros. Sci., 2025, 250: 112902
[29] Xu R T, Zhang C C, Wang G Q, et al. Molten salt stress corrosion of metal alloys—An updated review [J]. Sol. Energy Mater. Sol. Cells, 2025, 282: 113379
[30] Abe H, Watanabe Y, Miyazaki T. Characteristics of work hardened surface layer on austenitic stainless steels and its relation to SCC susceptibility in high temperature water [A]. Proceedings of the 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors [C]. Boston: American Nuclear Society, 2019: 165
[31] Li H, Wang D M, Wang X W, et al. Interaction between molten solar salt corrosion and creep loading on the high-temperature corrosion and cracking behavior of 316L stainless steel [J]. Eng. Fract. Mech., 2025, 315: 110791
[32] Wang J, Zhang E F, Yu C T, et al. Effect of Cr on stress corrosion behavior of typical pressure vessel materials in molten salt environment [J]. Sol. Energy Mater. Sol. Cells, 2025, 282: 113408
[33] Xiao X Z, Song D K, Chu H J, et al. Irradiation hardening for metallic materials [J]. Adv. Mech., 2015, 45: 201505
[33] 肖厦子, 宋定坤, 楚海建 等. 金属材料力学性能的辐照硬化效应 [J]. 力学进展, 2015, 45: 201505
[34] Wang Y, Lin J W, Wang C, et al. Research and modification direction of irradiation resistance of nickel-based alloy in high temperature nuclear reactor [J]. Mater. Rep., 2026, 40: 24110035
[34] 王 优, 林基伟, 王 晨 等. 高温反应堆用镍基合金辐照性能的研究进展及改性方向研究 [J]. 材料导报, 2026, 40: 24110035
[35] Zhu Z B, Huang H F, Lei G H, et al. Synergistic effect of irradiation and molten salt corrosion: Acceleration or deceleration? [J]. Corros. Sci., 2021, 185: 109434
[36] Lei G H, Li C, Jiang Z, et al. Irradiation accelerated fluoride molten salt corrosion of nickel-based UNS N10003 alloy revealed by X-ray absorption fine structure [J]. Corros. Sci., 2020, 165: 108408
[37] Liu K. Study of the irradiation effect and corrosion of domestically-made nickel-based alloy [D]. Shanghai: Shanghai Institute of Applied Physics, 2015
[37] 刘 可. 国产Ni基合金材料离子辐照与熔盐腐蚀效应研究 [D]. 上海: 中国科学院研究生院(上海应用物理研究所), 2015
[38] Ji W C, Zhu Z B, Huang H F, et al. Accelerated formation of M2C carbides by proton irradiation inhibits molten salt corrosion in Ni-based alloy [J]. J. Mater. Res. Technol., 2024, 33: 742
[39] Lin J B. Study on ion irradiation damage and molten salt corrosion mechanism of Hastelloy N alloy after-irradiation [D]. Shanghai: Shanghai Institute of Applied Physics, 2014
[39] 林建波. Hastelloy N合金的离子辐照损伤及辐照后熔盐腐蚀机理研究 [D]. 上海: 中国科学院研究生院(上海应用物理研究所), 2014
[40] Zhang S J. Study on ion irradiation effect and molten salt corrosion of Hastelloy N alloy after-irradiation [D]. Wuhan: Wuhan University, 2017
[40] 张胜军. Hastelloy N合金的离子辐照效应及辐照后熔盐腐蚀研究 [D]. 武汉: 武汉大学, 2017
[41] Zhu H L, Holmes R, Hanley T, et al. Effects of bubbles on high-temperature corrosion of helium ion-irradiated Ni-based alloy in fluoride molten salt [J]. Corros. Sci., 2017, 125: 184
[42] Evered C, Falconer C, Liu J L, et al. Synergistic effects of irradiation and molten salt corrosion influenced by grain boundary types and crystallographic orientation [J]. Corros. Sci., 2026, 258: 113385
[43] Ji W C, Zhu Z B, Huang H F, et al. Effect of irradiation damage defects on the impurity containing molten salt corrosion behavior in GH3535 alloy [J]. Corros. Sci., 2023, 223: 111475
[44] Lei G H, Yang S D, Huang H F, et al. Corrosion-driven outward migration and growth of helium bubbles in a nickel-based alloy in high-temperature molten salt environment [J]. Corros. Sci., 2019, 153: 47
[45] Liu M, Hou J, Han F F, et al. Effects of He ion irradiation on the corrosion performance of alloy GH3535 welded joint in molten FLiNaK [J]. Corros. Sci., 2019, 146: 172
[46] AlMousa N, Zhou W Y, Woller K B, et al. Effects of simultaneous proton irradiation on the corrosion of commercial alloys in molten fluoride salt [J]. Corros. Sci., 2023, 217: 111154
[47] El-Genk M S, Tournier J M. A review of refractory metal alloys and mechanically alloyed-oxide dispersion strengthened steels for space nuclear power systems [J]. J. Nucl. Mater., 2005, 340: 93
[48] Peng P, Ma Y F, Liu Z J, et al. Effect of Ta content on high temperature oxidation and hot corrosion resistance of DZ411 superalloy [J]. J. Iron Steel Res. Int., 2024, 31: 3109
[49] Ozeryanaya I N. Corrosion of metals by molten salts in heat-treatment processes [J]. Met. Sci. Heat Treat., 1985, 27: 184
[50] Rosenthal M W, Haubenreich P N, Briggs E B. Development status of molten-salt breeder reactors [R]. Oak Ridge: Oak Ridge National Laboratory, 1972
[51] McCoy H E. Status of materials development for molten salt reactors [R]. Oak Ridge: Oak Ridge National Laboratory, 1978
[52] Kasten P R, Bettis E S, Robertson R C. Design studies of 1000-MW(e) molten-salt breeder reactors [R]. Oak Ridge: Oak Ridge National Laboratory, 1966
[53] Lee M, Muránsky O, Karatchevtseva I, et al. Corrosion performance of Ni-based structural alloys for applications in molten-salt based energy systems: Experiment & numerical validation [J]. Corros. Sci., 2021, 190: 109607
[54] Briggs R B. Molten-salt reactor program semiannual progress report for period ending July 31, 1964 [R]. Oak Ridge: Oak Ridge National Laboratory, 1975
[55] Sankar K M, Singh P M. Effects of reducing impurity addition on corrosion and mechanical properties of structural materials in molten LiF-NaF-KF [J]. Corros. Sci., 2024, 227: 111702
[56] Xiao J B, Ren J D, Xiao S, et al. Corrosion behavior of different alloys in novel chloride molten salts for concentrating solar power plants [J]. Sol. Energy Mater. Sol. Cells, 2025, 286: 113531
[57] Goh B, Wang Y F, Nelaturu P, et al. Nobility vs. mobility: Insights into molten salt corrosion mechanisms of high-entropy alloys via high-throughput experiments and machine learning [J]. Matter, 2024, 7: 2313
[58] Klimenkov M, Lindau R, Möslang A. New insights into the structure of ODS particles in the ODS-Eurofer alloy [J]. J. Nucl. Mater., 2009, 386-388: 553
[59] Williams C A, Marquis E A, Cerezo A, et al. Nanoscale characterisation of ODS-Eurofer 97 steel: An atom-probe tomography study [J]. J. Nucl. Mater., 2010, 400: 37
[60] de Castro V, Marquis E A, Lozano-Perez S L, et al. Stability of nanoscale secondary phases in an oxide dispersion strengthened Fe-12Cr alloy [J]. Acta Mater., 2011, 59: 3927
[61] Williams C A, Unifantowicz P, Baluc N, et al. The formation and evolution of oxide particles in oxide-dispersion-strengthened ferritic steels during processing [J]. Acta Mater., 2013, 61: 2219
[62] Li C, Zhu Z B, Guo Q Y, et al. Positive role of Y2O3 nanoparticles/matrix interface in enhancing corrosion and irradiation resistance of oxide dispersion-strengthened Ni-based alloys in molten salt environments [J]. J. Mater. Res. Technol., 2025, 36: 2568
[63] Xu S, Chen L Z, Cao S G, et al. Research progress on microstructure design and control of ODS steels applied to advanced nuclear energy systems [J]. Mater. Rep., 2019, 33: 78
[63] 徐 帅, 陈灵芝, 曹书光 等. 先进核能系统用ODS钢的显微组织设计与调控研究进展 [J]. 材料导报, 2019, 33: 78
[64] Li C, Lei G H, Zhu Z B, et al. Effects of Y2O3 nanoparticles/Ni matrix interface on the mechanical properties and helium swelling resistance in NiMoCr-Y2O3 alloys [J]. J. Nucl. Mater., 2024, 589: 154854
[65] Zhang C, Lin L, Chen R C, et al. Grain boundary engineering and its effect on intergranular corrosion resistance of a Ni-Cr-Mo based C276 superalloy [J]. Crystals, 2022, 12: 1625
[66] Ma C Y, Zhang X F, Liu T G, et al. Grain boundary character distribution of Hastelloy C276 modified by thermo-mechanical processing [J]. MW Met. Form., 2025, (2): 105
[66] 马朝阳, 张晓峰, 刘廷光 等. 形变热处理调控哈氏合金C276的晶界特征分布 [J]. 金属加工(热加工), 2025, (2): 105
[67] Chen K, Zhou Y H, Shen Z, et al. Insights into the complexities of diffusion-induced grain boundary migration in Fe-Cr-Ni ternary alloys [J]. Acta Mater., 2026, 305: 121836
[68] Wang J M, Zhou Y H, Zhu T Y, et al. Sequential δ/γ interfacial degradation induces a sigmoidal kinetic transition in stress corrosion cracking during superlong-term thermal aging of duplex stainless steel [J]. Acta Mater., 2026, 313: 122314
[69] Yang W H, Zou J C, Li S, et al. Microstructure-dependent volatilization of Haynes 230 alloy in ultrahigh vacuum at high temperatures [J]. Corros. Sci., 2026, 265: 113821
[70] Wang C C, Zhang J M, Yu Z D, et al. Effect of grain boundary engineering on corrosion behavior and mechanical properties of GH3535 alloy in LiCl-KCl molten salt [J]. J. Nucl. Mater., 2025, 604: 155513
[71] Liu Y H, Yang C, Lu Y L, et al. Properties of protective coating on nickel alloy substrate against corrosion attack in fluoride salt [J]. Chin. J. Rare Met., 2015, 39: 865
[71] 刘艳红, 杨 超, 陆燕玲 等. 镍基合金耐氟盐腐蚀防护涂层的性能研究 [J]. 稀有金属, 2015, 39: 865
[72] Liu Q, Leng B, Qiu J, et al. Effect of graphite particles in molten LiF-NaF-KF eutectic salt on corrosion behaviour of GH3535 alloy [J]. Corros. Sci., 2020, 168: 108581
[73] Xu Y X, Zeng C L. Corrosion of materials for molten salt reactor [J]. J. Chin. Soc. Corros. Prot., 2014, 34: 211
[73] 徐雅欣, 曾潮流. 熔盐电堆的材料腐蚀 [J]. 中国腐蚀与防护学报, 2014, 34: 211
[74] Muralidharan G, Wilson D F, Santella M L, et al. Cladding alloys for fluoride salt compatibility final report [R]. Oak Ridge: Oak Ridge National Laboratory, 2011
[75] Wang Y G, Zhao Y W, Chen G, et al. Effect of average current density on micro-morphology and properties of pulse-electroplated Ni-W alloy coating [J]. Plat. Finish., 2010, 29(11): 8
[75] 王永光, 赵永武, 陈 广 等. 平均电流密度对脉冲镀镍钨合金微观形貌和性能的影响 [J]. 电镀与涂饰, 2010, 29(11): 8
[76] He X J, Song J L, Tan J, et al. SiC coating: An alternative for the protection of nuclear graphite from liquid fluoride salt [J]. J. Nucl. Mater., 2014, 448: 1
[77] Watanabe T, Kondo M, Nagasaka T, et al. Corrosion characteristic of AlN, Y2O3, Er2O3 and Al2O3 in flinak for molten salt blanket system [J]. Plasma Fus Res., 2010, 9: 342
[1] 韩恩厚, 王俭秋. 表面状态对核电关键材料腐蚀和应力腐蚀的影响[J]. 金属学报, 2023, 59(4): 513-522.
[2] 余春, 徐济进, 魏啸, 陆皓. 核级镍基合金焊接材料失塑裂纹研究现状[J]. 金属学报, 2022, 58(4): 529-540.
[3] 郭磊, 高远, 叶福兴, 张馨木. 航空发动机热障涂层的CMAS腐蚀行为与防护方法[J]. 金属学报, 2021, 57(9): 1184-1198.
[4] 王迪, 王栋, 谢光, 王莉, 董加胜, 陈立佳. Pt-Al涂层对一种镍基单晶高温合金抗热腐蚀行为的影响[J]. 金属学报, 2021, 57(6): 780-790.
[5] 余磊, 曹睿. 镍基合金焊接裂纹研究现状[J]. 金属学报, 2021, 57(1): 16-28.
[6] 华涵钰,谢君,舒德龙,侯桂臣,盛乃成,于金江,崔传勇,孙晓峰,周亦胄. W含量对一种高W镍基高温合金显微组织的影响[J]. 金属学报, 2020, 56(2): 161-170.
[7] 李克俭, 张宇, 蔡志鹏. 异种金属焊接接头在热-力耦合作用下的断裂位置转移机理[J]. 金属学报, 2020, 56(11): 1463-1473.
[8] 王资兴,黄烁,张北江,王磊,赵光普. 高合金化GH4065镍基变形高温合金点状偏析研究[J]. 金属学报, 2019, 55(3): 417-426.
[9] 刘汉青, 何超, 黄志勇, 王清远. TC17合金超高周疲劳裂纹萌生机理[J]. 金属学报, 2017, 53(9): 1047-1054.
[10] 韦康, 张麦仓, 谢锡善. 超超临界电站用镍基合金热加工过程的再结晶机理[J]. 金属学报, 2017, 53(12): 1611-1619.
[11] 欧美琼,刘扬,查向东,马颖澈,程乐明,刘奎. 一种新型镍基合金在超临界多种离子共存环境下的腐蚀行为*[J]. 金属学报, 2016, 52(12): 1557-1564.
[12] 谢君,于金江,孙晓峰,金涛,杨彦红. 温度对高W含量K416B镍基合金拉伸行为的影响*[J]. 金属学报, 2015, 51(8): 943-950.
[13] 谢君, 于金江, 孙晓峰, 金涛, 孙元. 高钨K416B铸造镍基合金高温蠕变期间碳化物演化行为[J]. 金属学报, 2015, 51(4): 458-464.
[14] 谢君,田素贵,刘姣,周晓明,苏勇. FGH95粉末镍基合金蠕变期间位错网的形成与分析[J]. 金属学报, 2013, 49(7): 838-844.
[15] 张姝,田素贵,于慧臣,于莉丽,于兴福. [111]取向镍基单晶合金在蠕变期间组织演化的有限元分析[J]. 金属学报, 2012, 48(5): 561-568.