The distribution and segregation behaviors of helium in tungsten Σ5(310)/[001] grain boundary region: A first-principles study-Reference-Cited by-同舟云学术

The distribution and segregation behaviors of helium in tungsten Σ5(310)/[001] grain boundary region: A first-principles study

Published:2024-03-01 Issue:9 Volume:135 Page:
ISSN:0021-8979
Container-title:Journal of Applied Physics
language:en
Short-container-title:

Author:

Wu Mingyu¹²³,Zhang Yujuan¹^ORCID,Li Yungang³,Hussain Muhammad Irfan¹,Jin Jingyuan¹,Li Sifan¹,Zhang Yu¹,Ge Changchun¹

Affiliation:

1. School of Materials Science and Engineering, University of Science and Technology Beijing (USTB) 1 , Beijing 100083, China

2. College of Science, North China University of Science and Technology 2 , Tangshan 063210, China

3. College of Metallurgy and Energy, North China University of Science and Technology 3 , Tangshan 063210, China

Abstract

In this work, the distribution and segregation behaviors of helium (He) and the effect of yttrium (Y) on these behaviors in the symmetrical tilt tungsten (W) Σ5(310)/[001] grain boundary (GB) region were studied using first-principles calculations. The results revealed that the GB has a significant impact on the behaviors of He in W. The solution and segregation energies of He in the W Σ5(310)/[001] GB region increase with increasing the distance from He to the GB and are inversely proportional to the effective electrons of He. The density of states analysis showed that the GB can suppress partial hybridization between He and W atoms. In addition, we find that the strengthening element Y facilitates the dissolution of He in the W GB region.

Funder

National Natural Science Foundation of China

International People-to-people Exchange in Science, Technology and Civillization

Publisher

AIP Publishing

Link

https://pubs.aip.org/aip/jap/article-pdf/doi/10.1063/5.0176209/19727923/095103_1_5.0176209.pdf

Reference47 articles.

1. Nuclear fusion: Status report and future prospects;Energy Policy,2016

2. Optimal configuration of a tokamak reactor with constraints moderately extrapolated from the ITER model;Fusion Eng. Des.,2019

3. Research progress in irradiation damage behavior of tungsten and its alloys for nuclear fusion reactor;Acta. Metall. Sin.,2019

4. Physics basis and design of the ITER plasma-facing components;J. Nucl. Mater.,2011

5. Preparation of ultrafine-grained/nanostructured tungsten materials: An overview;J. Alloys Compd.,2019