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作 者:全琪炜 刘向兵[1] 赵文增 吴奕初[2] 徐超亮[1] 张晏玮[1] 李远飞 钱王洁 贾文清 尹建 QUAN Qiwei;LIU Xiangbing;ZHAO Wenzeng;WU Yichu;XU Chaoliang;ZHANG Yanwei;LI Yuanfei;QIAN Wangjie;JIA Wenqing;YIN Jian(Suzhou Nuclear Power Research Institute Co.,Ltd.,Suzhou 215000,Jiangsu,China;School of Physics and Technology,Wuhan University,Wuhan 430000,China)
机构地区:[1]苏州热工研究院有限公司,江苏苏州215000 [2]武汉大学物理科学与技术学院,武汉430000
出 处:《材料导报》2024年第18期156-160,共5页Materials Reports
基 金:国家自然科学基金(11975171)。
摘 要:为探究两种典型燃料包壳锆合金Zr-4和Zr-1Nb辐照后的性能变化规律,本研究使用5.0 MeV的Xe离子室温辐照锆合金最高至4.0 dpa,并在360℃/18.6 MPa、0.01 mol/L LiOH溶液中开展最高28 d的腐蚀实验,结合纳米压痕、SEM和TEM,研究辐照硬化规律、腐蚀后的氧化膜形态及锆合金第二相的变化规律,讨论辐照对腐蚀的影响。结果表明,Xe离子辐照后两种锆合金产生了辐照硬化,Zr-1Nb比Zr-4辐照硬化率更高。在模拟环境腐蚀28 d内,Zr-4的耐腐蚀性优于Zr-1Nb,离子辐照增加了锆合金的腐蚀增重,且Zr-1Nb的辐照增强腐蚀效应更显著,辐照使锆合金第二相产生了不同程度的非晶化。研究结果有助于理解相关锆合金的辐照效应,为新型包壳锆合金材料开发及性能评估提供参考。In order to study the performance of two typical fuel cladding zirconium alloys Zr-4 and Zr-1Nb after irradiation,this study used 5.0 MeV Xe ions to irradiate the zirconium alloys up to 4.0 dpa at room temperature,and carried out the corrosion experiment at 360℃/18.6 MPa,0.01 mol/L LiOH solution for 28 d.Combined with nano-indentation,SEM and TEM,the irradiation hardening effect,the morphology of oxidation film and the change of second phase were characterized,discussing the effect of irradiation on corrosion.The result showed that both zirconium alloys produced irradiation hardening after Xe ion irradiation,with Zr-1Nb being more significant than Zr-4.The corrosion resistance of Zr-4 was better than Zr-1Nb in 28 d of simulated environmental corrosion.Ions irradiation increased the corrosion weight gain and caused the second phase amorphous,and the irradiation enhancing corrosion effect was more pronounced for Zr-1Nb.The research could help understand the irradiation effects of zirconium alloys and provide a reference for the development of new cladding zirconium alloy materials.
分 类 号:TL341[核科学技术—核技术及应用]
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