Effect of flow rate on corrosion behavior of 316L stainless steel welding seam in liquid lead bismuth eutectic
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摘要: 在核工业领域,316L不锈钢因其优异的性能常被作为核用钢种,液态铅铋合金常作为加速器次临界驱动系统(ADS)的冷却剂,高速流动的液态铅铋合金(LBE)会对316L不锈钢焊缝造成氧化腐蚀,同时氧化腐蚀后的产物也会对液态LBE造成污染,所以研究316L不锈钢焊缝在液态铅铋合金中的腐蚀行为具有重要意义. 文中对比研究了使用母材作为焊丝进行TIG焊的316L不锈钢焊缝在550 ℃动态(相对流速为1.70,2.31,2.98 m/s)液态LBE中的耐腐蚀性能,试验时间为1 500 h. 结果表明,三组试样都生成了双氧化层,外氧化层主要为Fe3O4,内氧化层主要为FeCr2O4,内氧化层相对于外氧化层较致密;随着流速的提高,元素的传质过程变快,氧化腐蚀加剧,内氧化层增厚.Abstract: Liquid lead bismuth eutectic (LBE) is often used as the coolant of Accelerator Driven Sub-critical System(ADS) in nuclear industry, and 316L stainless steel is often used as a nuclear stainless steel for its excellent performance. However, the high-speed liquid LBE will lead to the corrosion of 316L stainless steel welding seam and the corroded products will also pollute the liquid LBE, so the study of the corrosion resistance of 316L stainless steel welding seam in flowing liquid LBE is of great significance. This paper investigated the corrosion behavior of the Tungsten Inert Gas (TIG) welding seam of 316L stainless steel in inflowing liquid LBE at 550 °C for 1 500 hours (The relative flow rates were 1.70, 2.31 and 2.98 m/s). The results indicated that a double oxidation layer was generated on the surface of three groups of samples, and the outer oxide layer and the inner oxide layer were composed of the Fe3O4 and FeCr2O4, respectively. The compactness of the inner oxide layer is better than the outer oxide layer; With the increase of the relative flow rate, the mass transfer process of the elements became faster, the oxidation corrosion became more serious; and the inner oxide layer became thicker.
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Keywords:
- 316L stainless steel /
- welding seam /
- lead-bismuth eutectic /
- oxidation corrosion
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[1] Wu Yican, Huang Qunying, Bai Yunqing, et al. Preliminary experimental study on the corrosion of structural steels in liquid lead bismuth loop[J]. Chinese Journal of Nuclear Science and Enginee ring, 2010, 30(3): 238 − 243
[2] 吴宜灿, 黄群英, 柏云清, 等. 液态铅铋回路设计研制与材料腐蚀实验初步研究[J]. 核科学与工程, 2010, 30(3): 238 − 243 [3] Tuyle G J V, Todosow M, Aronson A L, et al. Accelerator-driven sub-critical target concept for transmutation of nuclear wastes[J]. Nuclear Technology (United States), 1991, 101(1): 1 − 17.
[4] Kurziusspencer M, Burgess J L, Harris R B, et al. Thermophysical properties of lead-bismuth eutectic alloy in reactor safety analyses[J]. Journal of Nuclear Science and Technology, 2006, 43(5): 526 − 536.
[5] 徐敬尧. 先进核反应堆用铅铋合金性能及纯净化技术研究[D]. 合肥: 中国科学技术大学, 2013. [6] Rao V S, Lim J, Hwang I S. Analysis of 316L stainless steel pipe of lead-bismuth eutectic cooled thermo-hydraulic loop[J]. Annals of Nuclear Energy, 2012, 48(12): 40 − 44.
[7] Zhang J. A review of steel corrosion by liquid lead and lead-bismuth[J]. Corrosion Science, 2009, 51(6): 1207 − 1227.
[8] Martín-Muñoz F J, Soler-Crespo L, Gómez-Briceño D. Assessment of the influence of surface finishing and weld joints on the corrosion/oxidation behaviour of stainless steels in lead bismuth eutectic[J]. Journal of Nuclear Materials, 2011, 416(1): 80 − 86.
[9] Yamaki E, Ginestar K, Martinelli L. Dissolution mechanism of 316L in lead-bismuth eutectic at 500 ℃[J]. Corrosion Science, 2011, 53(10): 3075 − 3085.
[10] Yeliseyeva O, Tsisar V, Benamati G. Influence of temperature on the interaction mode of T91 and AISI 316L steels with Pb-Bi melt saturated by oxygen[J]. Corrosion Science, 2008, 50(6): 1672 − 1683.
[11] Gossé S. Thermodynamic assessment of solubility and activity of iron, chromium, and nickel in lead bismuth eutectic[J]. Journal of Nuclear Materials, 2014, 449(s1–3): 122 − 131.
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