版权说明 操作指南
首页 > 成果 > 详情

Thermal shock resistance of TiN-, Cr-, and TiN/Cr-coated zirconium alloy

认领
导出
下载 Link by DOI
反馈
分享
QQ微信 微博
成果类型:
期刊论文
作者:
Xiao, Weiwei*;Chen, Huiqin;Liu, Xiaoshuang;Tang, Dewen;Deng, Hua*;...
通讯作者:
Xiao, Weiwei;Deng, Hua
作者机构:
[Liu, Xiaoshuang; Xiao, Weiwei; Chen, Huiqin; Tang, Dewen] Univ South China, Sch Mech Engn, Hengyang 421001, Hunan, Peoples R China.
[Liu, Xiaoshuang; Xiao, Weiwei; Zou, Shuliang; Chen, Huiqin; Tang, Dewen] Univ South China, Hunan Prov Key Lab Emergency Safety Technol & Equ, Hengyang 421001, Hunan, Peoples R China.
[Xiao, WW; Deng, Hua; Ren, Yuhong; Zhou, Xi; Lei, Ming; Xiao, Weiwei] CNNC Jianzhong Nucl Fuel Corp, Yibin 644000, Sichuan, Peoples R China.
通讯机构:
[Xiao, Weiwei] U
[Xiao, WW; Deng, H] C
Univ South China, Sch Mech Engn, Hengyang 421001, Hunan, Peoples R China.
CNNC Jianzhong Nucl Fuel Corp, Yibin 644000, Sichuan, Peoples R China.
语种:
英文
关键词:
Accidents;Adhesion;Coatings;Internal oxidation;Morphology;Scanning electron microscopy;Spectrometers;Surface morphology;Thermal expansion;Thermal shock;Tin alloys;Titanium nitride;X ray diffraction;Zircaloy;Zirconia;Accident tolerant fuels;Cross-sectional SEM image;Direct current magnetron sputtering;Energy dispersive spectrometers;Micro-structural properties;Sputtered coatings;Thermal shock resistance;Zr alloys;Titanium alloys
期刊:
Journal of Nuclear Materials
ISSN:
0022-3115
年:
2019
卷:
526
页码:
151777
基金类别:
This work was supported by CNNC funded project (Research on ATF technology), Operation Fund of Key Laboratory for Nuclear Reactor System Design (HT-KFKT-10-2018002) and the Opening Project of Cooperative Innovation Center for Nuclear Fuel Cycle Technology and Equipment, University of South China (2019KFY05). The authors are grateful to other participants of the project for their cooperation. This work was supported by CNNC funded project (Research on ATF technology), Operation Fund of Key Laboratory for Nuclear Reactor System Design ( HT-KFKT-10-2018002 ) and the Opening Project of Cooperative Innovation Center for Nuclear Fuel Cycle Technology and Equipment , University of South China ( 2019KFY05 ). The authors are grateful to other participants of the project for their cooperation.
机构署名:
本校为第一且通讯机构
院系归属:
机械工程学院
摘要:
As a candidate technology for accident tolerant fuel (ATF), surface modified Zr cladding has captured the interest of an army of nuclear workers in the past few years. In this paper, three coatings (TiN, Cr, and TiN/Cr) were deposited on Zr-4 by direct current magnetron sputtering. The microstructural properties of the three coatings were detected by using scanning electron microscope (SEM) and X-ray diffraction (XRD). The thickness of coating was determined by examining the cross sectional SEM image. The adhesion properties of was characterize...

反馈

验证码:
看不清楚,换一个
确定
取消

成果认领

标题:
用户 作者 通讯作者
请选择
请选择
确定
取消

提示

该栏目需要登录且有访问权限才可以访问

如果您有访问权限,请直接 登录访问

如果您没有访问权限,请联系管理员申请开通

管理员联系邮箱:yun@hnwdkj.com