美国材料研究学会(Materials Research Society,简称MRS)1995年秋季会议于1995年11月27日至12月1日在美国东部文化名城波士顿市举行。这是当今世界规模最大、水平最高的材料科学会议。近几年,每次会议都超过4000人。离子束材料改性一直...美国材料研究学会(Materials Research Society,简称MRS)1995年秋季会议于1995年11月27日至12月1日在美国东部文化名城波士顿市举行。这是当今世界规模最大、水平最高的材料科学会议。近几年,每次会议都超过4000人。离子束材料改性一直是MRS秋季会议中一个重要的分会。美国垒地亚国家实验室的Dr.S.T.Picraux作了关于半导体器件生产过程中的离子束技术的评述报告。展开更多
To shed a light on Xe bubble nucleation in U–Mo fuel from the view of primary irradiation damage,a reported U–Mo–Xe potential under the framework of embedded atom method has been modified within the range of short ...To shed a light on Xe bubble nucleation in U–Mo fuel from the view of primary irradiation damage,a reported U–Mo–Xe potential under the framework of embedded atom method has been modified within the range of short and intermediate atomic distance.The modified potential can better describe the interactions between energetic particles,and can accurately reproduce the threshold displacement energy surface calculated by the first-principles method.Then,molecular dynamics simulations of primary irradiation damage in U–Mo–Xe system have been conducted under different contents.The raise of Xe concentration brings about a remarkable promotion in residual defect quantity and generates bubbles in more overpressured state,which suggests an acceleration of irradiation damage under the accumulation of the fission gas.Meanwhile,the addition of Mo considerably reduces the residual defect count and hinders irradiation-induced Xe diffusion especially at high contents of Xe,corroborating the importance of high Mo content in mitigation of irradiation damage and swelling behavior in U–Mo fuel.In particular,the variation of irradiation damage with respect to contents suggests a necessity of taking into account the influence of local components on defect evolution in mesoscale simulations.展开更多
文摘美国材料研究学会(Materials Research Society,简称MRS)1995年秋季会议于1995年11月27日至12月1日在美国东部文化名城波士顿市举行。这是当今世界规模最大、水平最高的材料科学会议。近几年,每次会议都超过4000人。离子束材料改性一直是MRS秋季会议中一个重要的分会。美国垒地亚国家实验室的Dr.S.T.Picraux作了关于半导体器件生产过程中的离子束技术的评述报告。
基金Projects (50971072,51131003) support by the National Natural Science Foundation of ChinaProjects (2011CB606301,2012CB825700) supported by the Ministry of Science and Technology of ChinaProject supported by the Administration of Tsinghua University
基金the National Key Research and Development Program of China(Grant No.2017YFB0702401)the National Natural Science Foundation of China(Grant No.51631005).
文摘To shed a light on Xe bubble nucleation in U–Mo fuel from the view of primary irradiation damage,a reported U–Mo–Xe potential under the framework of embedded atom method has been modified within the range of short and intermediate atomic distance.The modified potential can better describe the interactions between energetic particles,and can accurately reproduce the threshold displacement energy surface calculated by the first-principles method.Then,molecular dynamics simulations of primary irradiation damage in U–Mo–Xe system have been conducted under different contents.The raise of Xe concentration brings about a remarkable promotion in residual defect quantity and generates bubbles in more overpressured state,which suggests an acceleration of irradiation damage under the accumulation of the fission gas.Meanwhile,the addition of Mo considerably reduces the residual defect count and hinders irradiation-induced Xe diffusion especially at high contents of Xe,corroborating the importance of high Mo content in mitigation of irradiation damage and swelling behavior in U–Mo fuel.In particular,the variation of irradiation damage with respect to contents suggests a necessity of taking into account the influence of local components on defect evolution in mesoscale simulations.
