Effect of material chemical composition on oxidation and stress corrosion cracking of the submerged arc welding Alloy 52M overlay in a simulated PWR primary water-Reference-Cited by-同舟云学术

Effect of material chemical composition on oxidation and stress corrosion cracking of the submerged arc welding Alloy 52M overlay in a simulated PWR primary water

Published:2024-01 Issue: Volume:588 Page:154753
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Xu Xinhe^ORCID,Jia Yibo,Pan Deng,Cui Tongming^ORCID,Lu Zhanpeng^ORCID,Lozano-Perez Sergio^ORCID,Chen Junjie,Li Shuangyan,Shoji Tetsuo

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference45 articles.

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2. Crack growth and cracking behavior of Alloy 600/182 and Alloy 690/152 welds in simulated PWR primary water;Lim;Nucl. Eng. Des.,2019

3. Microstructure of a safe-end dissimilar metal weld joint (SA508-52-316 L) prepared by narrow-gap GTAW;Ming;Mater. Charact,2017

4. Comparative study of microstructure and properties of low-alloy-steel/nickel-based-alloy interfaces in dissimilar metal weld joints prepared by different GTAW methods;Ming;Mater. Charact,2018

5. Characterization of low alloy ferritic steel–Ni base alloy dissimilar metal weld interface by SPM techniques, SEM/EDS, TEM/EDS and SVET;Wang;Mater. Charact,2015

Cited by 6 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. Assessing the influence of welding-induced mechanics on oxidation and stress corrosion cracking in an Alloy 600-Alloy 152 M weldment under simulated PWR primary water;Journal of Nuclear Materials;2024-12

2. Macroscopic and microscopic element distribution in transition zones of GTAW Alloy 52M weld joint and its PWSCC growth behaviour;Journal of Nuclear Materials;2024-12

3. Nano-micrometer scale characterization of PWSCC crack tips in the transition zone of 52M overlay and the implication to intergranular cracking;Journal of Nuclear Materials;2024-09

4. Ameliorating dilution of Cr and Ni and improving PWSCC resistance of 52 M overlay by hot wire plasma arc cladding;Journal of Materials Research and Technology;2024-07

5. Understanding Stress Corrosion Cracking (SCC), Affecting Variables and Prevention Strategies in Nuclear Power Plants—A Review;Arabian Journal for Science and Engineering;2024-06-11