Dynamic equilibrium of displacement damage defects in heavy-ion irradiated tungsten

被引:36
|
作者
Wang, Shiwei [1 ]
Guo, Wangguo [2 ]
Schwarz-Selinger, Thomas [3 ]
Yuan, Yue [4 ,5 ]
Ge, Lin [6 ]
Cheng, Long [4 ,5 ]
Zhang, Xiaona [6 ]
Cao, Xingzhong [2 ]
Fu, Engang [1 ]
Lu, Guang-Hong [4 ,5 ]
机构
[1] Peking Univ, Sch Phys, State Key Lab Nucl Phys & Technol, Beijing 100871, Peoples R China
[2] Chinese Acad Sci, Inst High Energy Phys, Beijing 100049, Peoples R China
[3] Max Planck Inst Plasma Phys, Boltzmannstr 2, D-85748 Garching, Germany
[4] Beihang Univ, Sch Phys, Beijing 100191, Peoples R China
[5] Beihang Univ, Beijing Key Lab Adv Nucl Mat & Phys, Beijing 100191, Peoples R China
[6] Beijing Univ Technol, Inst Microstruct & Property Adv Mat, Beijing 100124, Peoples R China
基金
中国国家自然科学基金;
关键词
Tungsten; Heavy-ion irradiation; Deuterium plasma exposure; Dynamic equilibrium of displacement damage; defects; Saturation of deuterium retention; IN-SITU TEM; RADIATION-DAMAGE; PURE TUNGSTEN; DEUTERIUM RETENTION; IMPLANTED TUNGSTEN; MOLECULAR-DYNAMICS; GRAIN-BOUNDARIES; DISLOCATION LOOP; NANOCRYSTALLINE; TEMPERATURE;
D O I
10.1016/j.actamat.2022.118578
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
How displacement damage defects generate and evolve in materials irradiated by energetic particles is a perennial topic in the field of nuclear materials. Here we experimentally reveal the dynamic equilibrium of displacement damage defects at room temperature and their subsequent influence on deuterium retention in tungsten. As irradiation dose increases, the major interstitial-type defects transform from dislocation loops (<= 0.1 dpa) to dislocation lines (0.1-0.15 dpa) and then to dislocation networks (>= 0.15 dpa), and finally the dy-namic equilibrium of defects featured by a stable microstructural configuration of the coexistence of networks and loops is reached (>= 0.2 dpa). In contrast, no significant changes in the dominant category of vacancy-type defects are observed above 0.05 dpa due to the higher migration barriers of vacancy clusters than interstitial clusters at room temperature. The defect dynamic equilibrium is confirmed via multiple results: the damage microstructure asymptoticly reaches a steady-state expressed by a constant density and size of defects, the hardness does not increase anymore, and the deuterium retention saturates. The nature of defect dynamic equilibrium is that the generation and annihilation of radiation defects restrict each other so that total defect content approaches an approximate constant under continual irradiation. Besides, we also verified the saturation of deuterium retention is inseparable from the defect dynamic equilibrium in a highly irradiated tungsten. These findings will convey some fresh insights into defect evolution and fuel inventory in tungsten and even other materials in the limit of high doses.
引用
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页数:15
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