Research Advance on Liquid Lead-Bismuth Eutectic Corrosion Resistant Si Enhanced Ferritic/Martensitic and Austenitic Stainless Steels

doi:10.11900/0412.1961.2022.00531

Acta Metall Sin

2023, Vol. 59

Issue (4): 502-512 DOI: 10.11900/0412.1961.2022.00531

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Research Advance on Liquid Lead-Bismuth Eutectic Corrosion Resistant Si Enhanced Ferritic/Martensitic and Austenitic Stainless Steels

WU Xinqiang, RONG Lijian(

), TAN Jibo, CHEN Shenghu, HU Xiaofeng, ZHANG Yangpeng, ZHANG Ziyu

CAS Key Laboratory of Nuclear Materials and Safety Assessment, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016, China

Cite this article:

WU Xinqiang, RONG Lijian, TAN Jibo, CHEN Shenghu, HU Xiaofeng, ZHANG Yangpeng, ZHANG Ziyu. Research Advance on Liquid Lead-Bismuth Eutectic Corrosion Resistant Si Enhanced Ferritic/Martensitic and Austenitic Stainless Steels. Acta Metall Sin, 2023, 59(4): 502-512.

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Abstract

Structural materials are one of the major factors that restrict the lead-cooled fast reactor construction due to metallic elements that can dissolve in the liquid lead-bismuth eutectic (LBE), which may affect the structure's safety. T91 steel and 316 stainless steel are the leading structural materials for critical equipment such as fuel cladding, reactor vessels, and reactor core internals. The environmental compatibility of those steels with the liquid LBE needs to be systematically evaluated. However, T91 steel and 316 stainless steel suffer from rapid oxidation corrosion in oxygen-saturated LBE at 550^oC. T91 steel's corrosion resistance in liquid LBE can be improved by decreasing the oxygen concentration (1.26 × 10^-6%, mass fraction), but dissolved corrosion occurred at dissolved oxygen concentration below 1 × 10^-6% for T91 steel and 316 stainless steel. T91 steel is sensitive to liquid metal embrittlement, significantly reducing its corrosion fatigue life in the liquid LBE. Compared to the standard (9%-12%)Cr ferritic/martensitic steel and 316 stainless steel, the microalloyed Si enhanced (9%-12%)Cr ferritic/martensitic steel (9Cr-Si and 12Cr-Si) and 316 stainless steel (ASS-Si) have good microstructural stability and comprehensive mechanical properties. The Si-rich oxide formation in liquid LBE improves the oxide film compactness and corrosion resistance. The dissolution corrosion was inhibited in static oxygen-saturation and oxygen-controlled (10^-6%-10^-7%) flowing liquid LBE (0.3 m/s) at 550^oC for 9Cr-Si, 12Cr-Si, and ASS-Si. These alloys are expected to meet the design requirements for a lead-cooled fast reactor.

Key words: ferritic/martensitic steel austenitic stainless steel liquid metal corrosion liquid metal embrittlement mechanical property microstructure stability

Received: 20 October 2022

ZTFLH:

TL341

Fund: National Natural Science Foundation of China(52271077);National Natural Science Foundation of China(51871218);LingChuang Research Project of China National Nuclear Corporation, and Youth Innovation Promotion Association CAS(2021189)

Corresponding Authors: RONG Lijian, professor, Tel: (024)23971979, E-mail: ljrong@imr.ac.cn

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	WU Xinqiang
	RONG Lijian
	TAN Jibo
	CHEN Shenghu
	HU Xiaofeng
	ZHANG Yangpeng
	ZHANG Ziyu

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https://www.ams.org.cn/EN/10.11900/0412.1961.2022.00531 OR https://www.ams.org.cn/EN/Y2023/V59/I4/502

Fig.1 Photos of corrosion damage test apparatuses in liquid lead-bismuth eutectic (LBE)
(a) immersion test apparatus (b) Pt/air sensor
(c) slow strain rate/creep test apparatus (d) fatigue test apparatus

Fig.2 Cross-section morphologies of oxide films on T91 steel after 1000 h exposure in liquid LBE at 550^oC and different mass fractions of dissolved oxygen (DO)^[4] (OOL—outer oxide layer, IOL—inner oxide layer, IOZ—inner oxide zone, OL—oxide layer)
(a) saturated oxygen (b) 1.26 × 10^-6% DO (c) 1.41 × 10^-8% DO (d) 1.12 × 10^-9% DO

Fig.3 Cross-sectional morphologies of oxide films on 316 stainless steel after 1000 h exposure in liquid LBE at 550^oC
(a) saturated oxygen (b) 1 × 10^-7% DO

Fig.4 Comparisons between fatigue life in air and liquid LBE (ASME—America Society of Mechanical Engineers)
(a) T91 steel (b) 316 stainless steel

Fig.5 Morphologies of fatigue crack propagation region in liquid LBE
(a) T91 steel, 350^oC, strain amplitude 0.6%
(b) 316 stainless steel, 400^oC, strain amplitude 0.8%

Fig.6 Cross-sectional back scattered electron (BSE) image (a) and corresponding line scanning (b) of 9Cr-Si alloy after exposure for 1000 h to stagn-ant oxygen-saturated LBE at 550^oC

Fig.7 LBE corrosion test results of 12Cr-Si ferritic/martensitic steels
(a) corrosion layer thickness changes with time in stagnant oxygen-saturated LBE at 550^oC (b, c) cross-sectional morphologies of HT9 steel (b) and 12Cr-Si steel (c) after exposure for 10000 h to stagnant oxygen-saturated LBE at 550^oC (d, e) cross-sectional morphologies and corresponding EDS element mappings of HT9 steel (d) and 12Cr-Si steel (e) after exposure to flowing and oxygen controlled LBE for 1500 h (0.3 m/s, 10^-6%-10^-7%)

Fig.8 SEM images of microstructures of as cast 9Cr-Si (a) and as-homogenized 9Cr-Si (b)

Fig.9 SEM image of tempered 9Cr-Si ferritic/martensitic steel

Fig.10 Strength curves at room temperature and high temperature (a) and ductile-to-brittle transition temperature (DBTT) curves (b) of 9Cr-Si and T91 steels

Fig.11 DBTT curves of tempered and aged 9Cr-Si steel at 550^oC (a), TEM image after 3000 h aging (b), and the elements mappings of the area denoted by the rectangle in Fig.11b (c)

Fig.12 Creep-rupture strength of 12Cr-Si and HT9 steels at 650^oC

Fig.13 Thicknesses of oxide scale of ASS-Si and 316 austenitic steels after exposure up to 5000 h to stagnant oxygen-saturated LBE at 550^oC

Fig.14 Cross-sectional BSE image (a) and corresponding EDS analyses (b,c) of ASS-Si austenitic steel after exposure for 1000 h to stagnant oxygen-saturated LBE at 550^oC

Fig.15 Cross-sectional SEM images of 316 (a,b) and ASS-Si (c,d) austenitic steels after exposure for 1500 h to flowing oxygen-controlled LBE at 550^oC (Figs.12b and d are enlarged views of the areas in Figs.11a and c, respectively)

Fig.16 TEM image and the corresponding element mappings of Cr, Ni, Si, and Fe near grain boundaries of Si-modified austenitic steel after aging at 550^oC for 1000 h

Table 1 Tensile and creep-rupture strength of Type 304 aus-tenitic steel and ASS-Si austenitic steel at 550^oC

1	Was G S. Challenges to the use of ion irradiation for emulating reactor irradiation [J]. J. Mater. Res., 2015, 30: 1158 doi: 10.1557/jmr.2015.73
2	OECD, Nuclear Energy Agency. Handbook on lead-bismuth eutectic alloy and lead properties, materials compatibility, thermalhydraulics and technologies [R]. OECD/NEA No. 6195, 2015
3	Gong X, Short M P, Auger T, et al. Environmental degradation of structural materials in liquid lead- and lead-bismuth eutectic-cooled reactors [J]. Prog. Mater. Sci., 2022, 126: 100920 doi: 10.1016/j.pmatsci.2022.100920
4	Zhu Z G, Zhang Q, Tan J B, et al. Corrosion behavior of T91 steel in liquid lead-bismuth eutectic at 550^oC: Effects of exposure time and dissolved oxygen concentration [J]. Corros. Sci., 2022, 204: 110405 doi: 10.1016/j.corsci.2022.110405
5	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]. Corros. Sci., 2008, 50: 1672 doi: 10.1016/j.corsci.2008.02.006
6	Martinelli L, Dufrenoy T, Jaakou K, et al. High temperature oxidation of Fe-9Cr-1Mo steel in stagnant liquid lead-bismuth at several temperatures and for different lead contents in the liquid alloy [J]. J. Nucl. Mater., 2008, 376: 282 doi: 10.1016/j.jnucmat.2008.02.006
7	Sapundjiev D, Van Dyck S, Bogaerts W. Liquid metal corrosion of T91 and A316L materials in Pb-Bi eutectic at temperatures 400-600^oC [J]. Corros. Sci., 2006, 48: 577 doi: 10.1016/j.corsci.2005.04.001
8	Klok O, Lambrinou K, Gavrilov S, et al. Effect of deformation twinning on dissolution corrosion of 316L stainless steels in contact with static liquid lead-bismuth eutectic (LBE) at 500^oC [J]. J. Nucl. Mater., 2018, 510: 556 doi: 10.1016/j.jnucmat.2018.08.030
9	Kurata Y, Futakawa M, Saito S. Comparison of the corrosion behavior of austenitic and ferritic/martensitic steels exposed to static liquid Pb-Bi at 450 and 550^oC [J]. J. Nucl. Mater., 2005, 343: 333 doi: 10.1016/j.jnucmat.2004.07.064
10	Tsisar V, Schroer C, Wedemeyer O, et al. Effect of structural state and surface finishing on corrosion behavior of 1.4970 austenitic steel at 400 and 500^oC in flowing Pb-Bi eutectic with dissolved oxygen [J]. J. Nucl. Eng. Rad. Sci., 2018, 4: 041001
11	Schroer C, Wedemeyer O, Skrypnik A, et al. Corrosion kinetics of Steel T91 in flowing oxygen-containing lead-bismuth eutectic at 450^oC [J]. J. Nucl. Mater., 2012, 431: 105 doi: 10.1016/j.jnucmat.2011.11.014
12	Tian S J. Growth and exfoliation behavior of the oxide scale on 316L and T91 in flowing liquid lead-bismuth eutectic at 480^oC [J]. Oxid. Met., 2020, 93: 183 doi: 10.1007/s11085-019-09953-7
13	Kolman D G. A review of recent advances in the understanding of liquid metal embrittlement [J]. Corrosion, 2019, 75: 42 doi: 10.5006/2904
14	Gong X, Stergar E, Marmy P, et al. Tensile fracture behavior of notched 9Cr-1Mo ferritic-martensitic steel specimens in contact with liquid lead-bismuth eutectic at 350^oC [J]. Mater. Sci. Eng., 2017, A692: 139
15	Wang H, Gong X, Xiao J, et al. Liquid metal embrittlement of 12Cr ferritic/martensitic steel thin-walled tubes exposed to liquid lead-bismuth eutectic [J]. Corros. Sci., 2022, 195: 110024 doi: 10.1016/j.corsci.2021.110024
16	Xue B Q, Tan J B, Zhang Z Y, et al. Effect of temperature on low cycle fatigue behavior of T91 steel in liquid lead-bismuth eutectic environment at 150-550^oC [J]. Int. J. Fatigue, 2023, 167: 107344 doi: 10.1016/j.ijfatigue.2022.107344
17	Gong X, Marmy P, Verlinden B, et al. Low cycle fatigue behavior of a modified 9Cr-1Mo ferritic-martensitic steel in lead-bismuth eutectic at 350^oC—Effects of oxygen concentration in the liquid metal and strain rate [J]. Corros. Sci., 2015, 94: 377 doi: 10.1016/j.corsci.2015.02.022
18	Vogt J B, Bouquerel J, Carle C, et al. Stability of fatigue cracks at 350 ^oC in air and in liquid metal in T91 martensitic steel [J]. Int. J. Fatigue, 2020, 130: 105265 doi: 10.1016/j.ijfatigue.2019.105265
19	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^oC [J]. J. Nucl. Mater., 2016, 468: 289 doi: 10.1016/j.jnucmat.2015.06.021
20	Van Den Bosch J, Coen G, Almazouzi A, et al. Fracture toughness assessment of ferritic-martensitic steel in liquid lead-bismuth eutectic [J]. J. Nucl. Mater., 2009, 385: 250 doi: 10.1016/j.jnucmat.2008.11.024
21	Auger T, Gorse D, Hamouche-Hadjem Z, et al. Fracture mechanics behavior of the T91 martensitic steel in contact with liquid lead-bismuth eutectic for application in an accelerator driven system [J]. J. Nucl. Mater., 2011, 415: 293 doi: 10.1016/j.jnucmat.2011.04.021
22	Weisenburger A, Jianu A, An W, et al. Creep, creep-rupture tests of Al-surface-alloyed T91 steel in liquid lead bismuth at 500 and 550^oC [J]. J. Nucl. Mater., 2012, 431: 77 doi: 10.1016/j.jnucmat.2011.11.027
23	Yurechko M, Schroer C, Skrypnik A, et al Creep-to-rupture of the steel P 92 at 650^oC in oxygen-controlled stagnant lead in comparison to air [J]. J. Nucl. Mater., 2013, 432: 78 doi: 10.1016/j.jnucmat.2012.07.029
24	Yurechko M, Schroer C, Skrypnik A, et al. Creep-to-rupture of 12Cr- and 14Cr-ODS steels in oxygen-controlled lead and air at 650^oC [J]. J. Nucl. Mater., 2014, 450: 88 doi: 10.1016/j.jnucmat.2013.09.063
25	Yurechko M, Schroer C, Wedemeyer O, et al. Creep-rupture tests on chromium-containing conventional and ODS steels in oxygen-controlled Pb and air at 650 ^oC[J]. Nucl. Eng. Des., 2014, 280: 686 doi: 10.1016/j.nucengdes.2014.06.003
26	Schroer C, Koch V, Wedemeyer O, et al. Silicon-containing ferritic/martensitic steel after exposure to oxygen-containing flowing lead-bismuth eutectic at 450 and 550^oC [J]. J. Nucl. Mater., 2016, 469: 162 doi: 10.1016/j.jnucmat.2015.11.058
27	Shi H, Jianu A, Fetzer R, et al. Compatibility and microstructure evolution of Al-Cr-Fe-Ni high entropy model alloys exposed to oxygen-containing molten lead [J]. Corros. Sci., 2021, 189: 109593 doi: 10.1016/j.corsci.2021.109593
28	Li N, Parker S S, Saleh T A, et al. Intermediate temperature corrosion behaviour of Fe-12Cr-6Al-2Mo-0.2Si-0.03Y alloy (C26M) at 300-600^oC [J]. Corros. Sci., 2019, 157: 274 doi: 10.1016/j.corsci.2019.05.029
29	Popovic M P, Chen K, Shen H, et al. A study of deformation and strain induced in bulk by the oxide layers formation on a Fe-Cr-Al alloy in high-temperature liquid Pb-Bi eutectic [J]. Acta Mater., 2018, 151: 301 doi: 10.1016/j.actamat.2018.03.041
30	Kurata Y. Corrosion behavior of Si-enriched steels for nuclear applications in liquid lead-bismuth [J]. J. Nucl. Mater., 2013, 437: 401 doi: 10.1016/j.jnucmat.2013.02.022
31	Short M P, Ballinger R G, Hänninen H E. Corrosion resistance of alloys F91 and Fe-12Cr-2Si in lead-bismuth eutectic up to 715^oC [J]. J. Nucl. Mater., 2013, 434: 259 doi: 10.1016/j.jnucmat.2012.11.010
32	Chen L Z, Tsisar V, Wang M, et al. Effect of oxygen on corrosion of an alumina-forming duplex steel in static liquid lead-bismuth eutectic at 550^oC [J]. Corros. Sci., 2021, 189: 109591 doi: 10.1016/j.corsci.2021.109591
33	Wang J, Lu S P, Rong L J, et al. Effect of silicon on the oxidation resistance of 9 wt.% Cr heat resistance steels in 550^oC lead-bismuth eutectic [J]. Corros. Sci., 2016, 111: 13 doi: 10.1016/j.corsci.2016.04.020
34	Shi H, Wang H, Fetzer R, et al. Influence of Si addition on the corrosion behavior of 9 wt% Cr ferritic/ martensitic steels exposed to oxygen-controlled molten Pb-Bi eutectic at 550 and 600^oC [J]. Corros. Sci., 2021, 193: 109871 doi: 10.1016/j.corsci.2021.109871
35	Ejenstam J, Szakálos P. Long term corrosion resistance of alumina forming austenitic stainless steels in liquid lead [J]. J. Nucl. Mater., 2015, 461: 164 doi: 10.1016/j.jnucmat.2015.03.011
36	Chen S H, Rong L J. Effect of silicon on the microstructure and mechanical properties of reduced activation ferritic/martensitic steel [J]. J. Nucl. Mater., 2015, 459: 13 doi: 10.1016/j.jnucmat.2015.01.004
37	Van Den Bosch J, Coen G, Hosemann P, et al. On the LME susceptibility of Si enriched steels [J]. J. Nucl. Mater., 2012, 429: 105 doi: 10.1016/j.jnucmat.2012.05.017
38	Gong X, Sun L, Zhang F F, et al. Effect of alloying elements on liquid metal embrittlement of pure BCC Fe in contact with liquid lead-bismuth eutectic: Experiments and first principles calculation [J]. Corros. Sci., 2022, 208: 110522 doi: 10.1016/j.corsci.2022.110522
39	Tan J B, Zhang Q, Wang X, et al. Slow tension and creep test device in high temperature liquid lead-bismuth environment [P]. Chin Pat, 202120775739.5, 2021
	谭季波, 张强, 王翔等. 高温液态铅铋环境中的慢拉伸及蠕变试验装置 [P]. 中国专利, 202120775739.5, 2021)
40	Tan J B, Zhang Q, Wang X, et al. A fatigue test device in high temperature liquid lead-bismuth environment [P]. Chin Pat, 2021207-75649.6, 2021
	谭季波, 张强, 王翔等. 一种高温液态铅铋环境中的疲劳试验装置 [P]. 中国专利, 202120775649.6, 2021)
41	Pan X, Zhang Y P, Dong Z H, et al. Effect of pre-oxidation treatment on the corrosion resistance in stagnant liquid Pb-Bi eutectic of 12Cr ferritic/martensitic steel [J]. Acta Metall. Sin., doi: 10.11900/0412.1961.2022.00267
	潘霞, 张洋鹏, 董志宏等. 预氧化处理对12Cr铁素体/马氏体钢耐Pb-Bi腐蚀性能的影响 [J]. 金属学报, doi: 10.11900/0412.1961.2022.00267
42	Roy A, Kumar P, Maitra D. The effect of silicon content on impact toughness of t91 grade steels [J]. J. Mater. Eng. Perform., 2009, 18: 205 doi: 10.1007/s11665-008-9271-z
43	Cabet C, Dalle F, Gaganidze E, et al. Ferritic-martensitic steels for fission and fusion applications [J]. J. Nucl. Mater., 2019, 523: 510 doi: 10.1016/j.jnucmat.2019.05.058
44	Chen S H, Xie A, Lv X L, et al. Tailoring microstructure of austenitic stainless steel with improved performance for generation-IV fast reactor application: A review [J]. Crystals, 2023, 13: 268 doi: 10.3390/cryst13020268
45	Wang Q Y, Chen S H, Rong L J. δ-Ferrite formation and its effect on the mechanical properties of heavy-section AISI 316 stainless steel casting [J]. Metall. Mater. Trans., 2020, 51A: 2998
46	Wang Q Y, Chen S H, Lv X L, et al. Role of δ-ferrite in fatigue crack growth of AISI 316 austenitic stainless steel [J]. J. Mater. Sci. Technol., 2022, 114: 7 doi: 10.1016/j.jmst.2021.10.008
47	Padilha A F, Rios P R. Decomposition of austenite in austenitic stainless steels [J]. ISIJ Int., 2002, 42: 325 doi: 10.2355/isijinternational.42.325
48	Etienne A, Radiguet B, Pareige P. Understanding silicon-rich phase precipitation under irradiation in austenitic stainless steels [J]. J. Nucl. Mater., 2010, 406: 251 doi: 10.1016/j.jnucmat.2010.08.045
49	Xie A, Chen S H, Wu Y, et al. Homogenization temperature dependent microstructural evolution and mechanical properties in a Nb-stabilized cast austenitic stainless steel [J]. Mater. Charact., 2022, 194: 112384 doi: 10.1016/j.matchar.2022.112384

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