Deformation mechanism-based true-stress creep model for SA508 Gr.3 steel over the temperature range of 450-750 °C

被引:19
作者
Lu, Chuanyang [1 ,2 ]
Wu, Xijia [3 ]
He, Yanming [1 ,4 ]
Gao, Zengliang [1 ,4 ]
Liu, Rong [2 ]
Chen, Ze [1 ]
Zheng, Wenjian [1 ]
Yang, Jianguo [1 ,4 ]
机构
[1] Zhejiang Univ Technol, Inst Proc Equipment & Control Engn, Hangzhou 310014, Zhejiang, Peoples R China
[2] Carleton Univ, Dept Mech & Aerosp Engn, Ottawa, ON K1S 5B6, Canada
[3] Natl Res Council Canada, Inst Aerosp Res, Struct & Mat Performance Lab, Ottawa, ON K1A 0R6, Canada
[4] Minist Educ, Engn Res Ctr Proc Equipment & Remfg, Beijing, Peoples R China
基金
中国国家自然科学基金;
关键词
Reactor pressure vessel; In-vessel retention; SA508; Gr.3; steel; Creep deformation mechanism; Creep model; REACTOR VESSEL; RETENTION; MELT; RPV; BEHAVIOR;
D O I
10.1016/j.jnucmat.2019.151776
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Stress and temperature effects on the creep behaviors and mechanisms of a typical nuclear reactor pressure vessel material, SA508 Gr.3 steel, are investigated, over the temperature range of 450-750 degrees C and stress range of 10-400 MPa. Because of the importance of creep life prediction for nuclear reactor failure prevention, three creep models are assessed: Orr-Sherby-Dorn (OSD) and Larson-Miller (LM) parameter methods, and deformation-mechanism based true-stress (DMTS) model. The OSD model employs a single activation energy Q and stress exponent n, which shows a large discrepancy between the experimental and predicted time-to-strain (3% and 5%) data with a coefficient of determination (R-2) less than 0.33 over the temperature range of 450-750 degrees C. Both the OSD and LM methods are effective in correlating the time-to-rupture with R-2 similar to 0.84 over a narrow temperature range of 650-750 degrees C. The DMTS creep model, on the other hand, characterizes the creep behavior in three normalized stress regions: low, intermediate and high, as dominated by grain boundary sliding (GBS), intragranular dislocation climb (IDC) and dislocation glide (IDG), respectively. The microstructural characteristics and creep damage mechanisms of SA508 Gr.3 steel are also examined using scanning/transmission electron microscopy to confirm the predominance of the aforementioned creep deformation mechanisms. The DMTS model provides a fully consistent description of the strain-time curves, the minimum creep rates (MCRs) and the time-to-strain/rupture as well. They are all in good agreement with the experimental observations, particularly with R-2 similar to 0.94, 0.995, and 0.79 for time to 3% strain, time to 5% strain, and time to rupture, respectively. These analyses demonstrate that the DMTS model is an effective tool in assessing creep properties of SA508 Gr.3 steel for in-vessel retention. (C) 2019 Elsevier B.V. All rights reserved.
引用
收藏
页数:10
相关论文
共 36 条
[11]   Grain boundary sliding revisited: Developments in sliding over four decades [J].
Langdon, TG .
JOURNAL OF MATERIALS SCIENCE, 2006, 41 (03) :597-609
[12]   Identifiying creep mechanisms at low stresses [J].
Langdon, TG .
MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, 2000, 283 (1-2) :266-273
[13]   Microstructural evolution and mechanical characterization for the A508-3 steel before and after phase transition [J].
Lu, Chuanyang ;
He, Yanming ;
Gao, Zengliang ;
Yang, Jianguo ;
Jin, Weiya ;
Xie, Zhigang .
JOURNAL OF NUCLEAR MATERIALS, 2017, 495 :103-110
[14]  
Lu CY., 2017, MATER SCI ENG, V711, P659
[15]   Structural integrity investigation for RPV with various cooling water levels under pressurized melting pool [J].
Mao, Jianfeng ;
Liu, Yunkai ;
Bao, Shiyi ;
Luo, Lijia ;
Lu, Zhiming ;
Gao, Zengliang .
MECHANICAL SCIENCES, 2018, 9 (01) :147-160
[16]   On the physical basis of a Larson-Miller constant of 20 [J].
Maruyama, K. ;
Abe, F. ;
Sato, H. ;
Shimojo, J. ;
Sekido, N. ;
Yoshimi, K. .
INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 2018, 159 :93-100
[17]   An assessment methodology for in-vessel cerium retention by external reactor vessel cooling during severe accidents in PWRs [J].
Park, JH ;
Jeong, YH ;
Baek, WP ;
Chang, SH .
ANNALS OF NUCLEAR ENERGY, 2001, 28 (12) :1237-1250
[18]   Detailed evaluation of melt pool configuration in the lower plenum of the APR1400 reactor vessel during severe accidents [J].
Park, Rae-Joon ;
Kang, Kyoung-Ho ;
Hong, Seong-Wan ;
Kim, Hwan-Yeol .
ANNALS OF NUCLEAR ENERGY, 2015, 75 :476-482
[19]   Characterization of heat transfer processes in a melt pool convection and vessel-creep experiment [J].
Sehgal, BR ;
Nourgaliev, RR ;
Dinh, TN .
NUCLEAR ENGINEERING AND DESIGN, 2002, 211 (2-3) :173-187
[20]   Creep resistance and material degradation of a candidate Ni-Mo-Cr corrosion resistant alloy [J].
Shrestha, Sachin L. ;
Bhattacharyya, Dhriti ;
Yuan, Guangzhou ;
Li, Zhijun J. ;
Budzakoska-Testone, Elizabeth ;
De Los Reyes, Massey ;
Drew, Michael ;
Edwards, Lyndon .
MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, 2016, 674 :64-75