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Frontiers in Energy

ISSN 2095-1701

ISSN 2095-1698(Online)

CN 11-6017/TK

Postal Subscription Code 80-972

2018 Impact Factor: 1.701

Front Energ Power Eng Chin    2009, Vol. 3 Issue (2) : 193-197    https://doi.org/10.1007/s11708-009-0030-0
RESEARCH ARTICLE
Feasibility analysis of modified AL-6XN steel for structure component application in supercritical water-cooled reactor
Xinggang LI(), Qingzhi YAN, Rong MA, Haoqiang WANG, Changchun GE
Institute of Nuclear Materials, University of Science and Technology Beijing, Beijing 100083, China
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Abstract

Modified AL-6XN austenite steel was patterned after AL-6XN superaustenitic stainless steel by introducing microalloy elements such as zirconium and titanium in order to adapt to recrystallizing thermo-mechanical treatment and further improve crevice corrosion resistance. Modified AL-6XN exhibited comparable tensile strength, and superior plasticity and impact toughness to commercial AL-6XN steel. The effects of aging behavior on corrosion resistance and impact toughness were measured to evaluate the qualification of modified AL-6XN steel as an in-core component and cladding material in a supercritical water-cooled reactor. Attention should be paid to degradation in corrosion resistance and impact toughness after aging for 50 hours when modified AL-6XN steel is considered as one of the candidate materials for in-core components and cladding tubes in supercritical water-cooled reactors.

Keywords supercritical water cooled reactor      tensile      impact toughness      corrosion      aging     
Corresponding Author(s): LI Xinggang,Email:xing-gangli@163.com   
Issue Date: 05 June 2009
 Cite this article:   
Xinggang LI,Qingzhi YAN,Rong MA, et al. Feasibility analysis of modified AL-6XN steel for structure component application in supercritical water-cooled reactor[J]. Front Energ Power Eng Chin, 2009, 3(2): 193-197.
 URL:  
https://academic.hep.com.cn/fie/EN/10.1007/s11708-009-0030-0
https://academic.hep.com.cn/fie/EN/Y2009/V3/I2/193
CMnPSSiNiCrMoCuCoN
ASTM0.030max2.00max0.040max0.030max1.00max23.50-25.5020.00-22.006.00-7.000.75max0.18-0.25
Typica0.0200.240.0200.00060.3124.3920.876.320.200.230.23
Tab.1  Chemical composition of AL-6XN []
Fig.1  Mass fraction of sigma phase and austenite (FCC_A1) vs temperature based on Thermo-Calc calculation
Fig.2  Microstructure of Mod AL-6XN steel
Fig.3  Comparison in tensile properties between Mod AL-6XN and commercial AL-6XN steel
Fig.4  Absorbed energy as a function of temperature in different heat-treated conditions
W.C.—water cooling; A.C. —air cooling
Fig.5  SEM image of microstructure of Mod AL-6XN after aging for 50 hours and exposure in aqua regia for 15 minutes
Fig.6  EDS analyses of polished and etched surface of Mod AL-6XN steel after aging for 50 hours
(a) The matrix; (b) precipitates along the grain boundary
Fig.7  Morphologies of polished surface of Mod AL-6XN with different heat treatments etched in aqua regia for 1 hour
(a) 1150°C 30 min; (b) 1150°C 60 min+600°C 26 h; (c) 1150°C 30 min+600°C 50 h
1 U.S. DOE Nuclear Energy Research Advisory Committee (NERAC) and the Generation IV International Forum (GIF). A technology roadmap for generation IV nuclear energy systems. GIF-002-00, Washington D C, 2002
2 Yoo J, Oka Y, Ishiwatari Y, . Thermo-mechanical analysis of supercritical pressure light water-cooled fast reactor fuel rod by FEMAXI-6 code. Annals of Nuclear Energy , 2006, 33 (17,18): 1379-1390
3 Liu Zhiming, Guo Juanyan, Shi Wenbao. The technological progress on material research and development for SCWR advanced reactor. The 3rd International Symposium on Supercritical Water-Cooled Reactors—Design and Technology, Shanghai, China , 2007
4 Allegheny Ludlum Corporation. Stainless steel AL-6XN alloy. UNS Designation N08367. Technical Data Blue Sheet, Pittsburgh, PA , 1998
5 Nemat-Nasser S, Guo Weiguo, Kihl D P. Thermomechanical response of AL-6XN stainless steel over a wide range of strain rates and temperatures. Journal of the Mechanics and Physics of Solids , 2001, 49(8): 1823-1846
doi: 10.1016/S0022-5096(00)00069-7
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