Nb稳定化奥氏体不锈钢在第四代核电领域的研究进展

陈胜虎, 谢昂, 杨彬彬, 刘涌涛, 陈思含, 赵明久, 姜海昌, 戎利建

Research Progress of the Niobium-Stabilized Austenitic Stainless Steels for Generation-IV Nuclear Reactors

CHEN Shenghu, XIE Ang, YANG Binbin, LIU Yongtao, CHEN Sihan, ZHAO Mingjiu, JIANG Haichang, RONG Lijian

图6 Alloy 709和HT-UPS奥氏体不锈钢经高温服役后的第二相形貌[76,77]及MC碳化物EDS分析

Fig.6 TEM images of secondary phase in Alloy 709 after aging at 650 oC for 500 h (Inset is the high magnification image of the dislocation (arrowed in Fig.6a)) (a)[76] and HT-UPS steel after creep-rupture test at 700 oC, 170 MPa for 18000 h (Inset is the analytical electron microscopy of MC carbides (arrowed in Fig.6b)) (b)[77]