奥氏体钢辐照促进应力腐蚀开裂行为机制的研究进展

高俊宣, 曹晗, 匡文军, 郑全, 张鹏, 钟巍华

Research Progress on Irradiation Assisted Stress Corrosion Cracking Behavior and Mechanism of Austenitic Steel

GAO Junxuan, CAO Han, KUANG Wenjun, ZHENG Quan, ZHANG Peng, ZHONG Weihua

图2 IASCC数据中CGR随应力强度因子和辐照温度的变化规律[16]

Fig.2 Variation of CGR with stress intensity factor (K) (a) and irradiation temperature (b) in IASCC datas[16] (The matrix of samples with different numbers in the figure is high purity 316L stainless steel, and the contents in brackets represent the alloying elements adulterated or removed), The K dependence of the Hf addition alloy samples PS01 (round symbols) and PS02 (square symbols) irradiated to 9.6 dpa and tested in NWC, HWC, and PWR water CGR as a function of temperature for solute addition alloys tested at NRI, SCK-CEN, and U-M in PWR at 288oC and 320oC