29th Symposium on Fusion Technology (SOFT 2016)

P2.179 The study of irradiation defects structure in tungsten: stability for the self-interstitial

6 Sep 2016, 14:20

1h 40m

Foyer 2A (2nd floor), 3A (3rd floor) (Prague Congress Centre)

Board: 179

Poster I. Materials Technology P2 Poster session

Speaker

Min Pan (Key Laboratory of Advanced Technology of Materials (Ministry of Education))

Description

Irradiation damage research is one of the basic issues to solve the application of first-wall materials in fusion engineering. The diffusion and recovery of the defects can greatly affect the performance of the materials in fusion. The rotation, stability, migration of the self-interstitial atoms (SIAs) in defect structures of tungsten is investigated by the first-principle method. It is found that the <11h>dumbbell have a lower formation energy than <111>dumbbell and a higher local charge density distribution in the self-interstitial atoms rotation. Further confirmation has been done from the uniaxial strain that the uniaxial modulus M of <11h> has a minimum value of 518Gpa in crystal tungsten. The results give a powerful evidence for the microscopic mechanisms of the stability of <11h> SIA style. Nevertheless, the <11h> SIA configure played an important role in the recovery process in irradiation damage.