【24h】

The Clustering of Cu atoms in Neutron Irradiated Reactor Pressure Vessel Steels Studied by Positron Annihilation

机译:正电子湮没中中子辐照反应器压力容器钢中CU原子的聚类

获取原文

摘要

Defect studies of neutron-irradiated Cr-Mo-V (VVER-440) type reactor pressure vessel steels were performed in the present work. The steels were irradiated in the nuclear power plant reactor under the conditions of a regular operation. Characterization of the irradiation induced defects was performed by two complementary techniques of positron annihilation spectroscopy: (ⅰ) positron lifetime spectroscopy was used for identification of defects and determination of defect densities, (ⅱ) coincidence Doppler broadening was employed for investigation of Cu atom aggregates. Long range diffusion of Cu atoms is assisted by the irradiation induced vacancies. The solute Cu atoms form small clusters in the irradiated steels. Subsequent isochronal annealing of the irradiated steel leads to vacancy assisted clustering of Cu atoms and formation of small precipitates. The Cu clusters exhibit maximum diameter at 400°C. Above this temperature the clusters dissolve again in the matrix.
机译:在本作工作中进行中子辐照的CR-MO-V(VVER-440)型反应器压力容器钢的缺陷研究。在常规操作的条件下,钢在核电厂反应器中照射。通过两种互补技术的正电子湮没光谱进行辐照诱导缺陷的表征:(Ⅰ)正电子寿命光谱用于鉴定缺陷和缺陷密度的测定,(Ⅱ)采用重合多普勒拓宽进行Cu原子聚集体的研究。通过辐射诱导的空位辅助Cu原子的长距离扩散。溶质Cu原子在辐照钢中形成小簇。辐照钢的随后的等时退火导致Cu原子的空位辅助聚类和小沉淀物的形成。 Cu簇在400℃下表现出最大直径。在该温度之上,簇在基质中再次溶解。

著录项

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号