Stress corrosion behavior of Alloy 690 in primary water of nuclear power plant

• 作 者: ChengtaoLi;AiRen;FeihuaLiu;YanLi;KeweiFang;
• 机 构: Suzhou Nuclear Power Research Institute,Suzhou,215004,China
• 出 处: 第三届核电厂材料与安全可靠性国际研讨会 (3rd MRNPP Symposium)
• 发表日期: 2013年期

　　strain test and slow strain rate test.The surface,cross section and fracture morphology were analyzed by scanning electron microscopy(SEM)and energy dispersive spectrometer(EDS).The results of SEM show that the surface is uniformly covered by oxide particles.The corrosion product is mainly consisted of spinel oxides of Fe,Ni and Cr.After 2100 hours corrosion test in primary water,no significant SCC is observed in the static load specimens.The surface condition has the great effect on the corrosion morphology.The slow strain specimens have the low susceptibility to SCC in primary water.The fracture morphology was the mixed mode of ductile fracture and brittle fracture.