A study of the effect of helium concentration and displacement damage on the microstructure of helium ion irradiated tungsten

被引:59
|
作者
Harrison, R. W. [1 ]
Greaves, G. [1 ]
Hinks, J. A. [1 ]
Donnelly, S. E. [1 ]
机构
[1] Univ Huddersfield, Sch Comp & Engn, Huddersfield HD1 3DH, W Yorkshire, England
基金
英国工程与自然科学研究理事会;
关键词
Tungsten; Irradiation; Fusion; Radiation damage; In situ TEM; NEUTRON-IRRADIATION; RADIATION-DAMAGE; TRANSMUTATION ELEMENTS; DISLOCATION LOOPS; ALLOYS; SUPERLATTICE; HE;
D O I
10.1016/j.jnucmat.2017.08.033
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Transmission electron microscopy (TEM) with in-situ He ion irradiation has been used to examine the damage microstructure of W when varying the helium concentration to displacement damage ratio, irradiation temperature and total dose. Irradiations employed 15, 60 or 85 keV He ions, at temperatures between 500 and 1000 degrees C up to doses of similar to 3.0 DPA. Once nucleated and grown to an observable size in the TEM, bubble diameter as a function of irradiation dose did not measurably increase at irradiation temperatures of 500 degrees C between 1.0 and 3.0 DPA; this is attributed to the low mobility of vacancies and He/vacancy complexes at these temperatures. Bubble diameter increased slightly for irradiation temperatures of 750 degrees C and rapidly increased when irradiated at 1000 degrees C. Dislocation loops were observed at irradiation temperatures of 500 and 750 degrees C and no loops were observed at 1000 degrees C. Burgers vectors of the dislocations were determined to be b = +/- 1/2<111> type only and both vacancy and interstitial loops were observed. The proportion of interstitial loops increased with He-appm/DPA ratio and this is attributed to the concomitant increase in bubble areal density, which reduces the vacancy flux for both the growth of vacancy-type loops and the annihilation of interstitial clusters. (C) 2017 Elsevier B.V. All rights reserved.
引用
收藏
页码:492 / 503
页数:12
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