Effects of low energy helium plasma irradiation on potassium doped tungsten

被引：15

作者：

Shu, Xiaoyan ^{[1
,2
]}

Huang, Bo ^{[1
]}

Liu, Dongping ^{[3
]}

Fan, Hongyu ^{[3
]}

Liu, Ning ^{[1
]}

Tang, Jun ^{[1
]}

机构：

[1] Sichuan Univ, Inst Nucl Sci & Technol, Key Lab Radiat Phys & Technol, Minist Educ, Chengdu, Peoples R China

[2] Southwest Univ Sci & Technol, Key Subject Lab Natl Def Radioact Waste & Environ, Mianyang, Peoples R China

[3] Dalian Nationalities Univ, Sch Phys & Mat Engn, Dalian, Peoples R China

来源：

FUSION ENGINEERING AND DESIGN | 2017年 / 117卷

基金：

中国国家自然科学基金;

关键词：

W-K; Spark plasma sintering; Helium; Irradiation; Defect; Microstructure; MICROSTRUCTURE; GROWTH; METALS;

D O I：

10.1016/j.fusengdes.2017.02.004

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

Effects of helium plasma irradiation on spark plasma sintering (SPS) W-K, pure W and traditionally sintered commercial W-K have been studied, concerning the density, grain size and potassium content as the influence factors. Pinholes are formed under 120 eV He ions at 600 degrees C and 1 x 10(23) m(-2) fluence on the surface of all samples. It is found that SPS-sintered W-K shows the best irradiation resistance among the present samples, and SPS-sintered pure W exhibits higher irradiation tolerance than commercial W-K. Different He-plasma tolerance was observed among the SPS-sintered W-K samples due to varied potassium content and grain size. In addition, the microstructure evolution under helium irradiation, the growth-migration of helium bubbles and their interactions of potassium bubbles have also been discussed. (C) 2017 Elsevier B.V. All rights reserved.

引用

页码：8 / 13

页数：6

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