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作 者:王研[1] 范红玉[1] 吕梦尧 周耿仟 关延民 牛金海[1]
机构地区:[1]大连民族学院物理与材料工程学院,大连116600
出 处:《核技术》2014年第12期23-28,共6页Nuclear Techniques
基 金:国家自然科学基金项目(No.11405023);辽宁省教育厅科研项目(No.L2014539);国家级大学生创新创业训练计划项目(No.G201412026039);大连民族学院"太阳鸟"学生科研项目(No.tyn2014353)资助
摘 要:钼(Mo)材料被作为托卡马克装置中面向等离子体材料的候选材料被广泛研究,因此研究钼材料的辐照损伤行为对于认识聚变堆关键材料的辐照损伤机制具有重要意义。采用低能(100 e V)、大流强(约1021 ions·m-2·s-1)He+在600 oC对钼样品进行辐照实验,考察了离子辐照剂量和退火温度变化对钼材料的表面损伤作用。分别采用扫描电镜(Scanning Electron Microscope,SEM)和无损伤的导电原子力显微镜(Conductive Atomic Force Microscopy,CAFM)检测技术对辐照前后样品的微观形貌、微结构演化以及内表面缺陷分布等进行了对比研究。结果表明,He+辐照会诱导钼样品晶粒尺寸的增加,钼材料表面的晶粒取向会影响辐照缺陷的分布。这对于探索抑制材料辐照损伤的新方法具有重要的指导意义。Background: Irradiation damage in materials has been of major interest for the nuclear materials community due to the needs to well understand and predict the behaviors of fusion reactor materials. Molybdenum (Mo) has been regarded as the potential candidates for the plasma-facing materials (PFMs) in Tokmak fusion reactors. Purpose: The understanding of the irradiation damage behavior of Mo is the major issue for development of key fusion reactors materials. Methods: Polycrystalline molybdenum materials have been irradiated with low-energy (100 eV) and high-flux (-10^21 ions·m^-2·s^-1) He+ at the irradiation temperature of 600℃. The effects of ion dose and annealing temperature on the surface damage of molybdenum are investigated. The morphology, microscopic evolution and distribution of defects of these samples before and after irradiation are compared using scanning electron microscopy (SEM) and non-destructive conductive atomic force microscopy (CAFM). Results: Analysis indicates that He+ irradiation can induce the increase of molybdenum sample grain size. The distribution of irradiation defect is depended on the grain orientation. The specific orientation of molybdenum material has a good performance in irradiation resistance. Conclusion: This work is of guiding significance to the exploration of the suppression of material irradiation damage.
分 类 号:TL627[核科学技术—核技术及应用]
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