Process Optimization and Tailored Mechanical Properties of a Nuclear Zr-4 Alloy Fabricated via Laser Powder Bed Fusion

Author:

Song Changhui1ORCID,Zou Zhuang1,Yan Zhongwei1,Liu Feng2,Yang Yongqiang1,Yan Ming3,Han Changjun1ORCID

Affiliation:

1. School of Mechanical and Automotive Engineering, South China University of Technology, Guangzhou 510641, China

2. Institute of Reactor Waste and Radiochemistry Research, China Nuclear Power Technology Research Institute Co., Ltd., Shenzhen 518028, China

3. Department of Materials Science and Engineering, Southern University of Science and Technology, Shenzhen 518055, China

Abstract

A nuclear Zr-4 alloy with a near full density was fabricated via laser powder bed fusion (LPBF). The influences of process parameters on the printability, surface roughness, and mechanical properties of the LPBF-printed Zr-4 alloy were investigated. The results showed that the relative density of the Zr-4 alloy samples was greater than 99.3% with the laser power range of 120–160 W and the scanning speed range of 600–1000 mm/s. Under a moderate laser power in the range of 120–140 W, the printed Zr-4 alloy possessed excellent surface molding quality with a surface roughness less than 10 µm. The microstructure of the printed Zr-4 alloy was an acicular α phase with an average grain size of about 1 µm. The Zr-4 alloy printed with a laser power of 130 W and a scanning speed of 400 mm/s exhibited the highest compression strength of 1980 MPa and the highest compression strain of 28%. The findings demonstrate the potential in the fabrication of complex Zr-4 alloy parts by LPBF for industrial applications.

Funder

Guangdong Basic and Applied Basic Research Foundation

Guangdong Province Science and Technology Project

National Natural Science Foundation of China

Special Support Foundation of Guangdong Province

Capital Health Development Scientific Research Project

Shenzhen Science and Technology Plan Project

Publisher

MDPI AG

Subject

Electrical and Electronic Engineering,Mechanical Engineering,Control and Systems Engineering

Reference44 articles.

1. Ninth International Symposium on Zirconium in the Nuclear Industry;Abe;J. Nucl. Sci. Technol.,1991

2. Texture development and anisotropic deformation of zircaloys;Charit;Prog. Nucl. Energy,2006

3. Materials challenges in nuclear energy;Zinkle;Acta Mater.,2013

4. Development and Characterization of Microstructure and Mechanical Properties of Heat-Treated Zr–2.5Nb Alloy for AHWR Pressure Tubes;Singh;Mater. Perform. Charact.,2013

5. Mechanical properties and microstructural evolution of ultrafine grained zircaloy-4 processed through multiaxial forging at cryogenic temperature;Fuloria;Trans. Nonferrous Met. Soc. China,2015

Cited by 2 articles. 订阅此论文施引文献 订阅此论文施引文献,注册后可以免费订阅5篇论文的施引文献,订阅后可以查看论文全部施引文献

同舟云学术

1.学者识别学者识别

2.学术分析学术分析

3.人才评估人才评估

"同舟云学术"是以全球学者为主线,采集、加工和组织学术论文而形成的新型学术文献查询和分析系统,可以对全球学者进行文献检索和人才价值评估。用户可以通过关注某些学科领域的顶尖人物而持续追踪该领域的学科进展和研究前沿。经过近期的数据扩容,当前同舟云学术共收录了国内外主流学术期刊6万余种,收集的期刊论文及会议论文总量共计约1.5亿篇,并以每天添加12000余篇中外论文的速度递增。我们也可以为用户提供个性化、定制化的学者数据。欢迎来电咨询!咨询电话:010-8811{复制后删除}0370

www.globalauthorid.com

TOP

Copyright © 2019-2024 北京同舟云网络信息技术有限公司
京公网安备11010802033243号  京ICP备18003416号-3