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Corrosion Behavior of Hastelloy N and 316L Stainless Steel in Molten LiF-NaF-KF |
Xiangbin DING,Hua SUN( ),Guojun YU,Xingtai ZHOU |
Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China |
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Abstract The corrosion behavior of Hastelloy N and 316L stainless steel (316L) in molten eutectic LiF-KF-NaF (FLiNaK) salt at 700 ℃ for 1000 h was investigated by means of static corrosion tests, while the corroded alloys were examined by SEM and EPMA. It was found that Hastelloy N and 316L all suffered from steady corrosion, while the corrosion resistance of Hastelloy N was superior to that of 316L. Hastelloy N experienced slight uniform corrosion, which was mainly due to the outward diffusion of Cr from the alloy. While 316L suffered from significant intergranular corrosion, which was related to the outward diffusion of Cr along grain boundaries. In addition, the mass loss of Hastelloy N firstly increased, and then degraded slowly with exposure time, which was mainly attributed to the re-deposition of Ni and Fe from the molten salt on the surface of Hastelloy N. The mass loss of 316L increased obviously for the first 400 h, and then became stable. The different in corrosion behavior of the two alloys in molten fluoride salt was mainly associated with their difference in chemical composition.
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[1] | Rosentha M W, Kasten P R, Briggs R B.Molten-salt reactors-history, status, and potential[J]. Nucl. Sci. Technol., 1970, 8(2): 107 | [2] | Macpherson H G.The molten-salt reactor adventure[J]. Nucl. Sci. Eng., 1985, 90(4): 374 | [3] | Rosenthal M W, Haubenreich P N, Briggs R B. The development status of molten-salt breeder reactors [R]. Oak Ridge: Union carbidecorporation, ORNL-4812, 1972 | [4] | Keiser J R.Corrosion of a platinum base alloy by components in a radio isotopic power-system[J]. J. Electrochem. Soc., 1977, 124(3): C94 | [5] | Manly W D, Coobs J H, Devan J H, et al.Metallurgical problems in molten fluoride systems [R]. Oak Ridge: Oak Ridge National Lab, 1958 | [6] | Xu Y X, Zeng C L.Corrosion of materials for molten salt reactor[J]. J. Chin. Soc. Corros. Prot., 2014, 34(3): 211 | [6] | (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(3): 211) | [7] | McCoy H E. Status of materials development for molten salt reactors [R].Oak Ridge: Oak Ridge National Lab, ORNL-TM-5920, 1978 | [8] | Lucas G E.The evolution of mechanical property change in irradiated austenitic stainless steels[J]. J. Nucl. Mater., 1993, 206(2/3): 287 | [9] | Angeliu T M, Ward J T, Witter J K.Assessing the effects of radiation damage on Ni-base alloys for the prometheus space reactor system[J]. J. Nucl. Mater., 2007, 366(1/2): 223 | [10] | Liu M, Lu Y L, Zhou X T.Investigation on microstructure of Hastelloy N after irradiation by 30 keV He ions[J]. Nucl. Tech., 2013, 36(5): 050205 | [10] | (刘敏, 陆燕玲, 周兴泰. 高温He离子辐照引起的Hastelloy N 合金微结构变化研究[J]. 核技术, 2013, 36(5): 050205) | [11] | lin J B, Li A G, He S M, et al. Investigation on corrosion resistance of Hastelloy N alloy after He+ ion irradiation[J]. Nucl. Tech., 2014, 37(5): 050601 | [11] | (林建波, 李爱国, 何上明等. He+离子辐照后Hastelloy N合金的耐腐蚀性研究[J]. 核技术, 2014, 37(5): 050601) | [12] | Dumerval M, Perrin S, Marchetti L, et al.Hydrogen absorption associated with the corrosion mechanism of 316L stainless steels in primary medium of pressurized water reactor (PWR)[J]. Corros. Sci., 2014, 85: 251 | [13] | Sona C S, Gajbhiye B D, Mathpati C S, et al.High temperature corrosion studies in molten salt-FLiNaK[J]. Corros. Eng. Sci. Technol., 2014, 49(4): 287 | [14] | Zhang L T, Wang J Q.Effect of dissolved oxygen content on stress corrosion cracking of a cold worked 316L stainless steel in simulated pressurized water reactor primary water environment[J]. J. Nucl. Mater., 2014, 446(1-3): 15 | [15] | Allen T R, McGaha J, Ball S, et al. FHR functional requirements and LBE identification white paper [R]. Berkeley: Department of Nuclear Engineering University of California, 2013 | [16] | Allen T R, Kohse G, Anderson M, et al.FHR materials, fuels and components white paper [R]. Madison: Department of Nuclear Engineering Physics University of Wisconsin, 2013 | [17] | Duan Z G, Zhang L F, Shi X Q, et al.Effect of Zn addition on composition of oxide scales formed on 316L stainless steel in high-temperature and high-pressured water[J]. J. Chin. Soc. Corros. Prot., 2014, 34(3): 249 | [17] | (段振纲, 张乐福, 石秀强 等. 注锌对316L奥氏体不锈钢氧化膜成分的影响 [J]. 中国腐蚀与防护学报, 2014, 34(3): 249) | [18] | Hai Z Y, Wang H, Hu Y, et al.Effect of Pt deposit on corrosion behavior of 316 LN in simulated primary loop water environment of pressurized water reactor[J]. J. Chin. Soc. Corros. Prot., 2014, 34(3): 253 | [18] | (海正银, 王辉, 胡勇等. 模拟压水堆一回路条件添加Pt技术研究[J]. 中国腐蚀与防护学报, 2014, 34(3): 253) | [19] | Ozeryanaya I N.Corrosion of metals by molten-salts in heat-treatment processes[J]. Met. Sci. Heat Treat., 1985, 27(3/4): 184 | [20] | Olson L C, Ambrosek J W, Allen T R, et al.Materials corrosion in molten LiF-NaF-KF salt[J]. J. Fluorine Chem., 2009, 130(1): 67 | [21] | Wang Y L, Liu H J, Zeng C L.Galvanic corrosion of pure metals in molten fluorides[J]. J. Fluorine Chem., 2014, 165(9): 1 | [22] | Keiser J R.Compatibility studies of potential molten-salt breeder reactor materials in molten fluoride salts [R]. Oak Ridge: Oak Ridge National Lab, ORNL-TM-5783, 1978 | [23] | Sabharwall P, Clark D, Glazoff M, et al.Advanced heat exchanger development for molten salts[J]. Nucl. Eng. Des., 2014, 280: 42 | [24] | Koger J. Corrosion and mass transfer characteristics of NaBF4-NaF(92.8 mole%) in Hastelloy N [R].Oak Ridge: Union carbide corporation, ORNL-TM-3866, 1972 |
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