Effect of Thermal Aging Temperature on Precipitation Behavior of Laves Phase and Impact Performance in High Si Content Ferritic Martensitic Steels

Zhou Jun; Qiu Shaoyu; Qiu Risheng; Zeng Wen; Wang Hao; Shu Ming; Yang Canxiang

doi:10.13832/j.jnpe.2022.05.0126

Volume 43 Issue 5

Oct. 2022

Turn off MathJax

Article Contents

Article Navigation > Nuclear Power Engineering > 2022 > 43(5): 126-132

Zhou Jun, Qiu Shaoyu, Qiu Risheng, Zeng Wen, Wang Hao, Shu Ming, Yang Canxiang. Effect of Thermal Aging Temperature on Precipitation Behavior of Laves Phase and Impact Performance in High Si Content Ferritic Martensitic Steels[J]. Nuclear Power Engineering, 2022, 43(5): 126-132. doi: 10.13832/j.jnpe.2022.05.0126

Citation:

Zhou Jun, Qiu Shaoyu, Qiu Risheng, Zeng Wen, Wang Hao, Shu Ming, Yang Canxiang. Effect of Thermal Aging Temperature on Precipitation Behavior of Laves Phase and Impact Performance in High Si Content Ferritic Martensitic Steels[J]. Nuclear Power Engineering, 2022, 43(5): 126-132. doi: 10.13832/j.jnpe.2022.05.0126

Citation:

Zhou Jun, Qiu Shaoyu, Qiu Risheng, Zeng Wen, Wang Hao, Shu Ming, Yang Canxiang. Effect of Thermal Aging Temperature on Precipitation Behavior of Laves Phase and Impact Performance in High Si Content Ferritic Martensitic Steels[J]. Nuclear Power Engineering, 2022, 43(5): 126-132. doi: 10.13832/j.jnpe.2022.05.0126

PDF( 12724 KB)

Effect of Thermal Aging Temperature on Precipitation Behavior of Laves Phase and Impact Performance in High Si Content Ferritic Martensitic Steels

doi: 10.13832/j.jnpe.2022.05.0126

1.
Nuclear Fuel and Material Institute, Nuclear Power Institute of China, Chengdu, 610213, China
2.
College of Materials Science and Engineering, Chongqing University, Chongqing, 400045, China

Received Date: 2021-10-11
Rev Recd Date: 2022-07-27
Publish Date: 2022-10-12

Abstract

Abstract

Ferritic martensitic steel (F/M steel) is one of the main candidate materials for lead-cooled fast reactor core. Increasing Si content can improve its corrosion resistance, but at the same time, it can promote the precipitation of Laves phase, thus affecting the toughness and plasticity of the material. For a F/M steel with a Si content of 0.98%, thermal aging experiments for 5000 h at three temperatures (500, 550 and 600℃) are carried out to study the effect of temperature on the precipitation behavior of Laves phase and impact performance. The results show that heating can promote the nucleation and coarsening of Laves phase, and with the temperature increasing from 550℃ to 600℃, the coarsening rate of Laves phase increases from 3.7 nm/h^1/3 to 9.0 nm/h^1/3. On the other hand, the increase of thermal aging temperature will accelerate the degradation of impact performance. After thermal aging at 550℃ and 600℃ for 500 h, the impact work (A_KV) decreases to 51% and 39% of that before thermal aging, respectively, while the A_KV value remains 75% of that before thermal aging for 2500 h at 500℃. The precipitation of Laves phase has a strong corresponding relationship with the degradation of impact performance, which is the main reason for the degradation of impact performance. egradation of impact performance.
- Ferritic martensitic steel (F/M steel),
- High Si content,
- Laves phase,
- Impact performance

FullText(HTML)

References(20)

References

[1]	PANAIT C G, BENDICK W, FUCHSMANN A, et al. Study of the microstructure of the Grade 91 steel after more than 100, 000 h of creep exposure at 600 C[J]. International Journal of Pressure Vessels and Piping, 2010, 87(6): 326-335. doi: 10.1016/j.ijpvp.2010.03.017
[2]	AITKALIYEVA A, HE L, WEN H, et al. 7- Irradiation effects in generation IV nuclear reactor materials[M]//YVON P. Structural Materials for Generation IV Nuclear Reactors. Duxford: Woodhead Publishing, 2017: 253-283.
[3]	BUCKTHORPE D. 1- introduction to generation IV nuclear reactor[M]//YVON P. Structural Materials for Generation IV Nuclear Reactors. Duxford: Woodhead Publishing, 2017: 1-22.
[4]	BARBIER F, BENAMATI G, FAZIO C, et al. Compatibility tests of steels in flowing liquid lead-bismuth[J]. Journal of Nuclear Materials, 2001, 295(2-3): 149-156. doi: 10.1016/S0022-3115(01)00570-0
[5]	MÜLLER G, HEINZEL A, KONYS J, et al. Results of steel corrosion tests in flowing liquid Pb/Bi at 420-600 C after 2000 hours[J]. Journal of Nuclear Materials, 2002, 301(1): 40-46. doi: 10.1016/S0022-3115(01)00725-5
[6]	KIPELOVA A, KAIBYSHEV R, BELYAKOV A, et al. Microstructure evolution in a 3%Co modified P911 heat resistant steel under tempering and creep conditions[J]. Materials Science and Engineering:A, 2011, 528(3): 1280-1286. doi: 10.1016/j.msea.2010.10.006
[7]	HOSOI Y, WADE N, KUNIMITSU S, et al. Precipitation behavior of Laves phase and its effect on toughness of 9Cr-2Mo ferritic-martensitic steel[J]. Journal of Nuclear Materials, 1986, 141-143: 461-467. doi: 10.1016/S0022-3115(86)80083-6
[8]	HU P, YAN W, SHA W, et al. Microstructure evolution of a 10Cr heat-resistant steel during high temperature creep[J]. Journal of Materials Science & Technology, 2011, 27(4): 344-351.
[9]	ISIK M I, KOSTKA A, EGGELER G. On the nucleation of Laves phase particles during high-temperature exposure and creep of tempered martensite ferritic steels[J]. Acta Materialia, 2014, 81: 230-240. doi: 10.1016/j.actamat.2014.08.008
[10]	ISIK M I, KOSTKA A, YARDLEY V A, et al. The nucleation of Mo-rich Laves phase particles adjacent to M₂₃C₆ micrograin boundary carbides in 12% Cr tempered martensite ferritic steels[J]. Acta Materialia, 2015, 90: 94-104. doi: 10.1016/j.actamat.2015.01.027
[11]	AGHAJANI A, RICHTER F, SOMSEN C, et al. On the formation and growth of Mo-rich Laves phase particles during long-term creep of a 12% chromium tempered martensite ferritic steel[J]. Scripta Materialia, 2009, 61(11): 1068-1071. doi: 10.1016/j.scriptamat.2009.08.031
[12]	DIMMLER G, WEINERT P, KOZESCHNIK E, et al. Quantification of the Laves phase in advanced 9-12% Cr steels using a standard SEM[J]. Materials Characterization, 2003, 51(5): 341-352. doi: 10.1016/j.matchar.2004.02.003
[13]	LI M M, CHEN W Y. Microstructure-based prediction of thermal aging strength reduction factors for grade 91 ferritic-martensitic steel[J]. Materials Science and Engineering:A, 2020, 798: 140116. doi: 10.1016/j.msea.2020.140116
[14]	XU Y T, NIE Y H, WANG M J, et al. The effect of microstructure evolution on the mechanical properties of martensite ferritic steel during long-term aging[J]. Acta Materialia, 2017, 131: 110-122. doi: 10.1016/j.actamat.2017.03.045
[15]	TKACHEV E, BELYAKOV A, KAIBYSHEV R. Creep strength breakdown and microstructure in a 9%Cr steel with high B and Low N contents[J]. Materials Science and Engineering:A, 2020, 772: 138821. doi: 10.1016/j.msea.2019.138821
[16]	CHEN S H, RONG L J. Effect of silicon on the microstructure and mechanical properties of reduced activation ferritic/martensitic steel[J]. Journal of Nuclear Materials, 2015, 459: 13-19. doi: 10.1016/j.jnucmat.2015.01.004
[17]	PHILIPPE T, VOORHEES P W. Ostwald ripening in multicomponent alloys[J]. Acta Materialia, 2013, 61(11): 4237-4244. doi: 10.1016/j.actamat.2013.03.049
[18]	AGHAJANI A, SOMSEN C, EGGELER G. On the effect of long-term creep on the microstructure of a 12% Chromium tempered martensite ferritic steel[J]. Acta Materialia, 2009, 57(17): 5093-5106. doi: 10.1016/j.actamat.2009.07.010
[19]	XU Y T, LI W, WANG M J, et al. Nano-sized MX carbonitrides contribute to the stability of mechanical properties of martensite ferritic steel in the later stages of long-term aging[J]. Acta Materialia, 2019, 175: 148-159. doi: 10.1016/j.actamat.2019.06.012
[20]	WANG W, XU G, SONG L L. Long-term stability of precipitated phases in CLAM steel during thermal aging[J]. Journal of Nuclear Materials, 2019, 521: 56-62. doi: 10.1016/j.jnucmat.2019.04.034