The effect of neutron irradiation on hydride reorientation and mechanical property degradation of zirconium alloy cladding-Reference-Cited by-同舟云学术

登录注册会员服务联系我们

The effect of neutron irradiation on hydride reorientation and mechanical property degradation of zirconium alloy cladding

Published:2017-10 Issue:7 Volume:49 Page:1472-1482
ISSN:1738-5733
Container-title:Nuclear Engineering and Technology
language:en
Short-container-title:Nuclear Engineering and Technology

Author:

Jang Ki-Nam,Kim Kyu-Tae

Funder

Dongguk University Research Fund

Nuclear Energy Development Program

National Research Foundation of Korea (NRF)

Ministry of Science, ICT and Future Planning

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference26 articles.

1. Hydride embrittlement in ZIRCALOY-4 plate: part II. Interaction between the tensile stress and the hydride morphology;Bai;Metall. Mater. Trans.,1994

2. A hydrogen uptake micro-mechanism for Zr alloys;Cox;J. Nucl. Mater.,1999

3. Cooling rate- and hydrogen content-dependent hydride reorientation and mechanical property degradation of Zr–Nb alloy claddings;Min;J. Nucl. Mater.,2013

4. Cladding cooling rate-dependent hydride reorientation and configuration;Kim;Korean J. Met. Mater.,2013

5. Effects of cooling rates on hydride reorientation and mechanical properties of zirconium alloy claddings under interim dry storage conditions;Min;Korean J. Met. Mater.,2013

Cited by 16 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

1. On the interaction of grain-scale and hydride-scale stresses in hydrogen enriched zirconium alloy nuclear cladding via combined discrete dislocation plasticity and crystal plasticity finite element modelling;Mechanics of Materials;2024-08

2. Micro-mechanisms of the ductile-to-brittle transition in hydrogenated zirconium alloys: A review and a comparison analysis of experimental data and theoretical approaches;Engineering Failure Analysis;2024-05

3. Study of the impact of hydrides on the fracture toughness of Zr-2.5Nb alloy;Nuclear Engineering and Design;2024-01

4. Review of the Radiation Effect on the Cladding of Zirconium Alloy in Nuclear Reactors;Lecture Notes in Mechanical Engineering;2024

5. Influence of Lubrication Effect on Microstructure of Hot Extruded Nuclear Grade Zr-4 Alloy;RARE METAL MAT ENG;2023

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