Heat-treatment optimization and heavy liquid metal compatibility of Si-enriched F/M steel for LFR structure application
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摘要: 針對自行制備的11Cr?1Si鐵素體/馬氏體不銹鋼開展了熱處理制度探索，及力學性能、鉛鉍環境靜態腐蝕和應力腐蝕行為研究。熱處理研究結果表明，11Cr?1Si不銹鋼在經過調質熱處理后（950 ℃/60 min+750 ℃/120 min）能夠在保證較高強度的同時獲得良好的韌性。500 ℃靜態腐蝕結果表明，11Cr?1Si在經過3368 h腐蝕后表面形成的氧化膜致密且連續，沒有出現開裂和脫落，并且整體氧化速率較緩慢，沒有觀察到鉛鉍向材料基體內的滲透，表現出良好的抗腐蝕性能。應力腐蝕實驗發現，11Cr?1Si不銹鋼在350 ℃和400 ℃下存在本征脆化，但是在450 ℃下沒有觀察到鉛鉍致脆現象。
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關鍵詞:
- 鉛基快堆 /
- 鐵素體/馬氏體不銹鋼 /
- 熱處理 /
- 鉛鉍腐蝕 /
- 液態金屬致脆
Abstract: The lead-cooled fast reactor (LFR) is one of six reactor concepts selected in the Generation IV Technology Roadmap and is perhaps the first to be applied commercially. Because the heavy liquid metal coolant has a severe corrosion effect on the core structure, the compatibility of the heavy liquid metal coolant and structural materials is recognized as a key limitation in the design and application of the LFR. Corrosion by heavy liquid metals such as liquid lead or lead–bismuth eutectic (LBE) is a physical or physical–chemical process involving surface oxidation, dissolution of material constituents, erosion corrosion, and fretting corrosion. Corrosion by heavy liquid metal can change the microstructure, composition, and surface morphology of structural materials, which will affect their mechanical and physical properties and lead to system failure. Currently, LFR research institutes are devoting great effort to the research and development of structural materials with good high-temperature mechanical properties and excellent corrosion and irradiation resistances. In this study, a series of experiments and analyses were performed on self-developed 11Cr?1Si ferritic/martensitic (F/M) steel, including heat treatment tests, mechanical tests, corrosion tests in static lead-bismuth eutectic (LBE), and slow strain-rate tests (SSRT) in LBE. The heat treatment results show that 11Cr?1Si steel obtains a good combination of high strength and toughness after quenching at 950 ℃ and tempering at 750 ℃. 11Cr?1Si steel was found to have good LBE corrosion resistance after exposure in static LBE for 3368 h, with a sufficiently low oxidation rate and a continuous and compact surface oxide layer, which protect the base metal of 11Cr?1Si from LBE penetration. The SSRT results show that the ductility of 11Cr?1Si in contact with LBE is sensitive to temperature, with loss of ductility observed at 350 ℃ and 400 ℃, but not at 450 ℃.-
Key words:
- LFR /
- ferritic/martensitic steel /
- heat treatment /
- LBE corrosion /
- liquid metal embrittlement
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圖 2 11Cr?1Si不銹鋼熱處理工藝過程
Figure 2. Schematic of heat treatment procedure for 11Cr?1Si steel
圖 3 液態鉛鉍環境腐蝕裝置。（a）靜態腐蝕；（b）慢應變速率拉伸測試
Figure 3. Photographs of LBE corrosion test apparatus: (a) static corrosion test apparatus; (b) slow strain?rate tensile test apparatus
圖 4 11Cr?1Si不銹鋼不同溫度淬火后掃描電鏡形貌。（a）900 ℃；（b）950 ℃；（c）1000 ℃；（d）1050 ℃；（e）1100 ℃
Figure 4. SEM images of 11Cr?1Si steel after water quenching at different temperatures: (a) 900 ℃; (b) 950 ℃; (c) 1000 ℃; (d) 1050 ℃; (e) 1100 ℃
圖 5 11Cr?1Si不銹鋼拉伸性能及不同溫度樣品斷口掃描電鏡照片。（a）拉伸實驗結果；（b）室溫；（c）200 ℃；（d）400 ℃；（e）600 ℃；（f）650 ℃
Figure 5. Tensile properties and SEM images of fracture surface of 11Cr?1Si steel at different temperatures: (a) tensile results; (b) room temperature; (c) 200 ℃; (d) 400 ℃; (e) 600 ℃; (f) 650 ℃
圖 6 12Cr CNS樣品1000 h腐蝕形貌。（a）截面腐蝕形貌；（b）能譜分析區域；（c～g）Bi、Pb、O、Fe、Cr元素面分布分析結果
Figure 6. Corrosion results of 12Cr CNS after 1000 h exposure in static LBE: (a) SEM image of cross section; (b) map analysis area; (c–g) distributions of different elements
圖 7 11Cr?1Si樣品1000 h腐蝕形貌。（a）截面腐蝕形貌；（b）能譜分析區域；（c～h）Bi、Pb、O、Fe、Cr、Si元素面分布分析結果
Figure 7. Corrosion results of 11Cr?1Si after 1000 h exposure in static LBE: (a) SEM image of cross section; (b) map analysis area; (c–h) distributions of different elements
圖 8 12Cr CNS樣品2000 h腐蝕結果。（a）截面腐蝕形貌；（b）能譜線掃描區域；（c）線掃描結果
Figure 8. Corrosion results of 12Cr CNS after 2000 h exposure in static LBE: (a) SEM image of cross section; (b) EDS line scan area; (c) line scan results
圖 9 11Cr?1Si樣品2000 h腐蝕結果。（a）截面腐蝕形貌；（b）能譜線掃描區域；（c）線掃描結果
Figure 9. Corrosion results of 11Cr?1Si after 2000 h exposure in static LBE: (a) SEM image of cross section; (b) EDS line scan area; (c) line scan results
圖 10 12Cr CNS樣品3368 h腐蝕結果。（a）截面腐蝕形貌；（b）能譜線掃描區域；（c）線掃描結果
Figure 10. Corrosion results of 12Cr CNS after 3368 h exposure in static LBE: (a) SEM image of cross section; (b) EDS line scan area; (c) line scan results
圖 11 11Cr?1Si樣品3368 h腐蝕結果。（a）截面腐蝕形貌；（b）能譜線掃描區域；（c）線掃描結果
Figure 11. Corrosion results of 11Cr?1Si after 3368 h exposure in static LBE: (a) SEM image of cross section; (b) EDS line scan area; (c) line scan results
圖 12 兩種材料在500 ℃靜態鉛鉍中的氧化動力學曲線
Figure 12. Oxidation curves in static LBE at 500 ℃ for 12Cr CNS and 11Cr?1Si steels
圖 13 11Cr?1Si鋼不同溫度慢應變速率拉伸曲線。（a）350 ℃；（b）400 ℃；（c）450 ℃
Figure 13. Slow strain rate tensile curves of 11Cr?1Si steel at different temperatures: (a) 350 ℃; (b) 400 ℃; (c) 450 ℃
圖 14 11Cr?1Si不銹鋼350 ℃鉛鉍環境拉伸樣品斷口照片
Figure 14. Fracture surface of 11Cr?1Si specimen tested at 350 ℃ in LBE
圖 15 11Cr?1Si不銹鋼450 ℃鉛鉍環境拉伸樣品斷口照片
Figure 15. Fracture surface of 11Cr?1Si specimen tested at 450 ℃ in LBE
表 1 9/12Cr CNS和11Cr?1Si不銹鋼主要合金元素對照
Table 1. Chemical composition of 9/12Cr CNS and 11Cr?1Si steels
Material Chemical composition (mass fraction) /% Fe Cr Ni Mo W Mn V Si Ti 11Cr?1Si Bal. 10.87 0.69 0.73 0.61 0.81 0.30 0.91 0.07 9Cr CNS Bal. 9.55 0 0.48 1.21 0.6 0.26 0.05 0.05 12Cr CNS Bal. 12.0 0 1.0 1.1 1.0 0.2 0.15 0.03 
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表 2 11Cr?1Si不銹鋼淬火溫度對δ-鐵素體含量的影響
Table 2. Area fraction variation of δ-ferrite as a function of austenitization temperature of 11Cr?1Si steel
Austenitization temperature/℃ Area fraction of δ-ferrite/% 900 14.9 950 13.7 1000 13.4 1050 12.7 1100 14.8
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表 3 11Cr?1Si不銹鋼熱處理溫度對沖擊韌性的影響
Table 3. Charpy impact energy of 11Cr?1Si steel after heat treatment at various temperatures
Category Austenitization temperature + tempering temperature/℃ Absorbing energy/J Variation of austenitization temperature 950 + 750 64.02 1000 + 750 50.15 1050 + 750 15.30 Tempering temperature variation 950 + 700 44.92 950 + 750 64.02 950 + 800 75.94
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參考文獻
[1] Alemberti A. The lead fast reactor: an opportunity for the future? Engineering, 2016, 2(1): 59 doi: 10.1016/J.ENG.2016.01.022 [2] Allen T R, Crawford D C. Lead-cooled fast reactor systems and the fuels and materials challenges. Sci Technol Nucl Installations, 2007: 097486 [3] Allen T R, Sridharan K, Tan L, et al. Materials challenges for generation IV nuclear energy systems. Nucl Technol, 2008, 162(3): 342 doi: 10.13182/NT08-A3961 [4] Fazio C, Sobolev V, Aerts A, et al. Handbook on Lead-bismuth Eutectic Alloy and Lead Properties, Materials Compatibility, Thermal-hydraulics and Technologies. 2015 Ed. Issy-les-Moulineaux: OECD, 2015 [5] Zhang J S. A review of steel corrosion by liquid lead and lead–bismuth. Corros Sci, 2009, 51(6): 1207 doi: 10.1016/j.corsci.2009.03.013 [6] Wang J M, Farzin A, Du D H, et al. Electrochemical corrosion behaviors of 316L stainless steel used in PWR primary pipes. Chin J Eng, 2017, 39(9): 1355汪家梅, Farzin Arjmand, 杜東海, 等. 壓水堆一回路主管道316L不銹鋼的電化學腐蝕行為. 工程科學學報, 2017, 39(9):1355 [7] Barbier F, Benamati G, Fazio C, et al. Compatibility tests of steels in flowing liquid lead–bismuth. J Nucl Mater, 2001, 295(2-3): 149 doi: 10.1016/S0022-3115(01)00570-0 [8] Zhao X, Yan Q Z, Zeng X, et al. Preliminary research on corrosion behavior of vacuum smelting-casting ODS steel in lead-bismuth eutectic. Progr Rep China Nucl Sci Technol, 2019, 6: 92趙熹, 燕青之, 曾獻, 等. 熔鑄ODS鋼液態鉛鉍腐蝕行為初步研究. 中國核科學技術進展報告, 2019, 6:92 [9] Chernov V M, Kardashev B K, Moroz K A. Low-temperature embrittlement and fracture of metals with different crystal lattices–Dislocation mechanisms. Nucl Mater Energy, 2016, 9: 496 doi: 10.1016/j.nme.2016.02.002 [10] Gabriele F D, Amore S, Scaiola C, et al. Corrosion behaviour of 12Cr-ODS steel in molten lead. Nucl Eng Des, 2014, 280: 69 doi: 10.1016/j.nucengdes.2014.09.030 [11] Xu Y L, Zhang J Q, Chu F M, et al. Compatibility of 9Cr2WVTa and 12CrWTi-ODS steel with flowing Pb. Ann Rep China Inst Atom Energy, 2008: 4 [12] Schroer C, Konys J. Quantification of the long-term performance of steels T91 and 316L in oxygen-containing flowing lead-bismuth eutectic at 550 ℃. J Eng Gas Turbines Power, 2010, 132(8): 082901 doi: 10.1115/1.4000364 [13] Schroer C, Wedemeyer O, Novotny J, et al. Performance of 9% Cr steels in flowing lead-bismuth eutectic at 450 and 550 C, and 10–6 mass% dissolved oxygen. Nucl Eng Des, 2014, 280: 661 doi: 10.1016/j.nucengdes.2014.01.023 [14] Zhang J S. Long-term behaviors of oxide layer in liquid lead–bismuth eutectic (LBE), Part I: model development and validation. Oxid Met, 2013, 80(5-6): 669 doi: 10.1007/s11085-013-9450-7 [15] Ye C Q, Vogt J B, Serre I P. Liquid metal embrittlement of the T91 steel in lead bismuth eutectic: The role of loading rate and of the oxygen content in the liquid metal. Mater Sci Eng A, 2014, 608: 242 doi: 10.1016/j.msea.2014.04.082 [16] Kolman D G. A review of recent advances in the understanding of liquid metal embrittlement. Corrosion, 2019, 75(1): 42 doi: 10.5006/2904 [17] Long B, Tong Z, Groschel F, et al. Liquid Pb–Bi embrittlement effects on the T91 steel after different heat treatments. J Nucl Mater, 2008, 377(1): 219 doi: 10.1016/j.jnucmat.2008.02.050 [18] Van den Bosch J, Bosch R W, Sapundjiev D, et al. Liquid metal embrittlement susceptibility of ferritic–martensitic steel in liquid lead alloys. J Nucl Mater, 2008, 376(3): 322 doi: 10.1016/j.jnucmat.2008.02.008 [19] Auger T, Lorang G. Liquid metal embrittlement susceptibility of T91 steel by lead–bismuth. Scripta Mater, 2005, 52(12): 1323 doi: 10.1016/j.scriptamat.2005.02.027 [20] Van den Bosch J, Coen G, Hosemann P, et al. On the LME susceptibility of Si enriched steels. J Nucl Mater, 2012, 429(1-3): 105 doi: 10.1016/j.jnucmat.2012.05.017 [21] Yang X, Liao B, Liu J, et al. Embrittlement phenomenon of China low activation martensitic steel in liquid Pb–Bi. Acta Metall Sin, 2017, 53(5): 513 doi: 10.11900/0412.1961.2016.00576楊旭, 廖波, 劉堅, 等. 中國低活化馬氏體鋼在液態Pb–Bi中的脆化現象. 金屬學報, 2017, 53(5):513 doi: 10.11900/0412.1961.2016.00576 [22] Gong X, Marmy P, Qin L, et al. Temperature dependence of liquid metal embrittlement susceptibility of a modified 9Cr–1Mo steel under low cycle fatigue in lead–bismuth eutectic at 160–450 ℃. J Nucl Mater, 2016, 468: 289 doi: 10.1016/j.jnucmat.2015.06.021 [23] Chen Y X, Yan Q Z, Zhang X X, et al. Microstructure characteristics and properties of yttrium-bearing 9Cr ferritic-martensitic steel cladding tubes. Mater Res Express, 2019, 6(9): 0965c6 doi: 10.1088/2053-1591/ab332e [24] Dai Y, Long B, Groeschel F. Slow strain rate tensile tests on T91 in static lead–bismuth eutectic. J Nucl Mater, 2006, 356(1-3): 222 doi: 10.1016/j.jnucmat.2006.05.039 [25] Shchukin E D. Physical–chemical mechanics in the studies of Peter A. Rehbinder and his school. Colloids Surf A, 1999, 149(1-3): 529 doi: 10.1016/S0927-7757(98)00607-4 [26] Klecka J, Gabriele F D, Hojna A. Mechanical properties of the steel T91 in contact with lead. Nucl Eng Des, 2015, 283: 131 doi: 10.1016/j.nucengdes.2014.10.004 -
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