赵卓

• 1:东北大学材料科学与工程学院

摘要(Abstract)：

研究了15Cr12MoVN钢室温和高温拉伸性能与回火处理温度的关系,采用扫描电镜(SEM)和透射电镜(TEM)等方法对其拉伸断口形貌和显微组织进行分析。结果表明:随回火温度由700℃增至780℃,15Cr12MoVN钢室温和高温拉伸强度逐渐降低,塑性改善;800℃回火处理引起二次硬化现象,730～780℃回火处理后钢的拉伸性能基本保持稳定,优于700℃和800℃回火处理;各回火温度下的拉伸断口均呈现韧窝型韧性断裂特征。综合考虑拉伸性能和冲击韧性的匹配,适宜于15Cr12MoVN钢的回火温度区间为730～765℃。

关键词(KeyWords)： 15Cr12MoVN;回火温度;拉伸性能;拉伸断口

Abstract:

Keywords:

基金项目(Foundation):

作者(Author): 赵卓

DOI: 10.13289/j.issn.1009-6264.2018-0296

参考文献(References)：

• [1] 戎利建,张玉妥,陆善平,等.铅与铅铋共晶合金手册[M].北京:科学出版社,2013:571-572.
• [2] Rosenwasser S N,Miller P,Dalessandro J A,et al.The application of martensitic stainless steels in long lifetime fusion first wall/blankets[J].Journal of Nuclear Materials,1979,85/86:177-182.
• [3] 朱宝田,赵毅.我国超超临界燃煤发电技术的发展[J].华电技术,2008,30(2):1-5.ZHU Bao-tian,ZHAO Yi.Domestic development of ultra-supercritical power technology[J].Huadian Technology,2008,30(2):1-5.
• [4] Yokoyama T,Masuyama F.Application of boiler materials for ultra-high temperature and high pressure power plants[J].The Thermal and Nuclear Power,1994,45(11):43-54.
• [5] Bagley K Q,Ehrlich K,Calza B A.European development of ferritic-martensitic steels for fast reactor wrapper applications[J].Nuclear Energy,1988,27(5):295-309.
• [6] Raj B,Vijayalashmi M.Ferritic steels for sodium-cooled fast reactors:design principles and challenges[J].JOM,2010,62(9):75-83.
• [7] Klueh R L.Elevated-temperature ferritic and martensitic steels and their application to future nuclear reactors[M].Oak Ridge,Tennessee:Oak Ridge National Laboratory,2004:10-32.
• [8] Anderoglu O,Byun T S,Toloczko M,et al.Mechanical performance of ferritic martensitic steels for high dose applications in advanced nuclear reactors[J].Metallurgical and Materials Transactions A,2013,44A:S70-S83.
• [9] Cheon J S,Lee C B,Lee B O,et al.Sodium fast reactor evaluation:core materials[J].Journal of Nuclear Materials,2009,392(9):324-330.
• [10] Gelles D S.Microstructural development in reduced activation ferritic alloys irradiated to 200 dpa at 420 ℃[J].Journal of Nuclear Materials,1994,s212/215:714-719.
• [11] Shikakura S,Nomura S,Ukai S,et al.Development of high-strength ferritic/martensitic steel for FBR core materials[J].Journal of Atomic Energy Society of Japan,1991,33(12):1157-1170.
• [12] 赵卓.回火处理对15Cr12MoVN钢显微组织和冲击吸收功的影响[J].材料热处理学报,2017,38(12):50-56.ZHAO Zhuo.Effects of tempering on microstructure and impact absorbed energy of 15Cr12MoVN martensitic steel[J].Transactions of Materials and Heat Treatment,2017,38(12):50-56.
• [13] Masuyama F.History of power plants and progress in heat resistant steels[J].ISIJ International,2001,41(6):612-625.
• [14] Yan W,Wang W,Shan Y,et al.9-12Cr Heat-resistant Steels[M].Switzerland:Springer International Publishing,2015:47-50.
• [15] Abe F,Noda T,Araki H,et al.Development of reduced-activation martensitic 9Cr steels for fusion reactor[J].Journal of Nuclear Science and Technology,1994,31(4):279-292.
• [16] Klueh R L,Alexander D J.Heat treatment effects on impact toughness of 9Cr-1MoVNb and 12Cr-1MoVW steels irradiated to100dpa[J].Journal of Nuclear Materials,1998,258/263:1269-1274.
• [17] Klueh R L,Kai J J,Alexander D J.Microstructure-mechanical properties correlation of irradiated conventional and reduced-activation martensitic steels[J].Journal of Nuclear Materials,1995,255(3):175-186.
• [18] Maruyama K,Sawada K,Koike J.Strengthening mechanisms of creep resistant tempered martensitic steel[J].ISIJ International,2001,41(6):641-653.
• [19] Abe F,Kern T U,Viswanathan R.Creep-resistant Steels[M].New York:CRC Press,2008:279-301.
• [20] Santella M L.Influence of chemical compositions on lower ferrite-austenite transformation temperatures in 9%Cr Steels[J].Journal of Pressure Vessel Technology,2010,134(2):1-5.
• [21] 崔彤,王磊,杨洪才,等.长期时效对一种镍基合金组织及冲击性能的影响[J].有色矿冶,2005,21(1):33-36.CUI Tong,WANG Lei,YANG Hong-cai,et al.Microstructures and impact toughness of a Ni-based superalloy after long-term aging[J].Non-Ferrous Mining and Metallurgy,2005,21(1):33-36.
• [22] Chan B L,Jin S C,Kim S H,et al.Metal fuel development and verification for prototype generation IV sodium-cooled fast reactor[J].Nuclear Engineering and Technology,2016,48(5):1096-1108.

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