Effects of surface grinding for scratched alloy 690TT tube in PWR nuclear power plant: Microstructure and stress corrosion cracking-Reference-Cited by-同舟云学术

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Effects of surface grinding for scratched alloy 690TT tube in PWR nuclear power plant: Microstructure and stress corrosion cracking

Published:2022-06 Issue: Volume:113 Page:229-245
ISSN:1005-0302
Container-title:Journal of Materials Science & Technology
language:en
Short-container-title:Journal of Materials Science & Technology

Author:

Wu Bin,Ming Hongliang,Meng Fanjiang,Li Yifeng,He Guangqing,Wang Jianqiu,Han En-Hou

Publisher

Elsevier BV

Subject

Materials Chemistry,Metals and Alloys,Polymers and Plastics,Mechanical Engineering,Mechanics of Materials,Ceramics and Composites

Reference41 articles.

1. Stress corrosion crack initiation in Alloy 690 in high temperature water

2. Electrochemical properties and growth mechanism of passive films on Alloy 690 in high-temperature alkaline environments

3. Effects of 405 stainless steel on crevice corrosion behavior of Alloy 690 in high-temperature pure water

4. Materials challenges in nuclear energy

5. Quantitative Assessment of Submodes of Stress Corrosion Cracking on the Secondary Side of Steam Generator Tubing in Pressurized Water Reactors: Part 1

Cited by 18 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. Effects of high-temperature and high-pressure immersion corrosion durations on the fretting tribo-corrosion behaviors of Inconel 690 alloy;Wear;2024-11

2. Investigation of hydrogen embrittlement sensitivity of X65 pipeline steel with different compositions employing thermal simulation;International Journal of Hydrogen Energy;2024-09

3. Application of Machine Learning and Deep Learning Techniques for Corrosion and Cracks Detection in Nuclear Power Plants: A Review;Arabian Journal for Science and Engineering;2024-08-12

4. Effect of fretting wear regimes on stress corrosion cracking of Alloy 690TT in high-temperature pressurized water;Corrosion Science;2024-08

5. Effect of the triangular prism dent on stress corrosion cracking behavior of alloy 690TT heat transfer tube in a lead-containing alkaline solution;Journal of Nuclear Materials;2024-06

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