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| Corrosion Behavior of 304 and 316H Stainless Steels in Molten LiF-NaF-KF |
Hui LIU1,2,Wei QIU1( ),Bin LENG2( ),Guojun YU2 |
1. School of Energy and Power Engineering, Changsha University of Scinece & Technology, Changsha 410114, China 2. Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China |
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Abstract The corrosion behavior of 304 and 316H stainless steels in molten LiF-NaF-KF(FLiNaK) salt at 700 ℃ was studied by static immersion test, followed by SEM/EDS and EPMA analyses. Results show that the corrosion characteristics of the two stainless steels in molten FLiNaK salt are mainly selective depletion of Cr from the surface and grain boundaries underneath the surface. The corrosion depth and weight loss of 316H stainless steel are lower than those of 304 stainless steel, which may be ascribed to the Mo addition in 316H steel. After corrosion, the two steels show surface corrosion layers enriched in Ni and Fe, as well as nano-sized precipitates in the steel matrix near the surface. EDS analyses suggest these precipitates to be Cr and Al nitrides or carbonitrides. The formation of these precipitates significantly increases the hardness of the materials.
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Received: 02 January 2018
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| Fund: Supported by National Natural Science Foundation of China(51301025);Supported by National Natural Science Foundation of China(51141001);Supported by National Natural Science Foundation of China(51501217) |
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Corresponding Authors:
Wei QIU,Bin LENG
E-mail: hncsqqwk86@163.com;lengbin@sinap.ac.cn
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| [1] | Cai X Z, Dai Z M, Xu H J. Thorium molten salt reactor nuclear energy system [J]. Physics, 2016, 45: 578 | | [1] | 蔡翔舟, 戴志敏, 徐洪杰. 钍基熔盐堆核能系统 [J]. 物理, 2016, 45: 578 | | [2] | Jiang M H, Xu H J, Dai Z M. Advanced fission energy program-TMSR nuclear energy system [J]. Bull. Chin. Acad. Sci., 2012, 27: 366 | | [2] | 江绵恒, 徐洪杰, 戴志敏. 未来先进核裂变能——TMSR核能系统 [J]. 中国科学院院刊, 2012, 27: 366 | | [3] | Serp J, Allibert M, Benes O, et al. The molten salt reactor (MSR) in generation IV: Overview and perspectives [J]. Prog. Nucl. Energ., 2014, 77, 308 | | [4] | Williams D F. Assessment of candidate molten salt coolants for the NGNP/NHI Heat Transfer Loop [R]. Oak Ridge: Oak Ridge National Lab, 2006 | | [5] | Zhu Y S, Hou J, Yu G J, et al. Effects of exposing temperature on corrosion performance of weld joint of a Ni-Mo-Cr alloy [J]. J. Fluorine Chem., 2016, 182: 69 | | [6] | Olson L C, Ambrosek J W, Sridharan K, et al. Materials corrosion in molten LiF-NaF-KF salt [J]. J. Fluorine Chem., 2009, 130: 67 | | [7] | Wang Y L, Liu H J, Yu G J, et al. Electrochemical study of the corrosion of a Ni-based alloy GH3535 in molten (Li, Na, K) F at 700 ℃ [J]. J. Fluorine Chem., 2015, 178: 14 | | [8] | Charalampos A, Anselmo T C, Alexandre Y K C, et al. Technical description of the “mark 1” pebble-bed fluoride-salt-cooled high-temperature reactor (PB-FHR) power plant [R]. UCBTH-14-002. Berkeley: Department of Nuclear Engineering University of California, 2014 | | [9] | Sellers R S, Cheng W J, Kelleher B C, et al. Corrosion of 316L stainless steel alloy and Hastelloy-N superalloy in molten eutectic LiF-NaF-KF salt and interaction with graphite [J]. Nucl. Technol., 2014, 188: 192 | | [10] | Zheng G Q. Corrosion behavior of alloys in molten fluoride salts [D]. Wisconsin: The University of Wisconsin-Madison, 2015 | | [11] | Ding X B, Sun H, Yu G J, et al. Corrosion behavior of Hastelloy N and 316L stainless steel in molten LiF-NaF-KF [J].Chin J.. Soc. Corros. Prot., 2015, 35: 543 | | [11] | 丁祥彬, 孙华, 俞国军等. Hastelloy N合金和316L不锈钢在LiF-NaF-KF熔盐中的腐蚀行为研究 [J]. 中国腐蚀与防护学报, 2015, 35: 543 | | [12] | Koger J W. Alloy compatibility with LiF-BeF2 salts containing ThF4 and UF4 [R]. ORNL-4286. Oak Ridge: Oak Ridge National Lab, 1972 | | [13] | Kondo M, Nagasaka T, Sagara A, et al. Metallurgical study on corrosion of austenitic steels in molten salt LiF-BeF2 [J]. J. Nucl. Mater., 2009, 386: 685 | | [14] | Williams D F, Toth L M, Clarno K T. Assessment of candidate molten salt coolants for the Advanced high-temperature Reactor (AHTR) [R]. ORNL/TM-2006/12. Oak Ridge: Oak Ridge National Lab, 2006 | | [15] | Schneider M, Kremmer K, L?mmel C, et al. Galvanic corrosion of metal/ceramic coupling [J]. Corros. Sci., 2014, 80: 191 | | [16] | Ozeryanaya I N. Corrosion of metals by molten salts in heat-treatment processes [J]. Met. Sci. Heat Treat., 1985, 27: 184 | | [17] | Zeng C L, Li J, Zhou T. Galvanic corrosion in molten salts: A discussion of the corrosion mechanism of two-phase Ni-20Cr-20/30Cu alloys in eutectic (Li, K)2CO3 at 650 ℃ [J]. Oxid. Met., 2005, 64: 207 | | [18] | Fontana M G, Staehle R W. Chromium depletion and void formation in Fe-Ni-Cr alloys during molten salt corrosion and related processes [A]. In: Koger J W. Advances in Corrosion Science and Technology [M]. New York: Plenum Press, 1974 | | [19] | Ouyang F Y, Chang C H, You B C, et al. Effect of moisture on corrosion of Ni-based alloys in molten alkali fluoride FLiNaK salt environments [J]. J. Nucl. Mater., 2013, 437: 201 | | [20] | Zhang S L, Li M J, Wang X B, et al. Intergranular corrosion of 18-8 austenitic stainless steel [J].Chin J.. Soc. Corros. Prot., 2007, 27: 124 | | [20] | 张述林, 李敏娇, 王晓波等. 18-8奥氏体不锈钢的晶间腐蚀 [J]. 中国腐蚀与防护学报, 2007, 27: 124 | | [21] | Smith A F. The diffusion of chromium in type 316 stainless steel [J]. Met. Sci., 1975, 9: 375 | | [22] | Olson L C, Sridharan K, Anderson M, et al. Intergranular corrosion of high temperature alloys in molten fluoride salts [J]. Mater. High Temp., 2010, 27: 145 | | [23] | Bruemmer S M. Grain boundary chemistry and intergranular failure of austenitic stainless steels [J]. Mater. Sci.Forum, 1989, 46: 309 | | [24] | Zheng G Q, He L F, Carpenter D, et al. Corrosion-induced microstructural developments in 316 stainless steel during exposure to molten Li2BeF4 (FLiBe) salt [J]. J. Nucl. Mater., 2016, 482: 147 |
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