Stress-assisted oxidation behaviour of inconel 52M/316 austenitic stainless-steel dissimilar weld joints in a simulated pressurised water reactor
Author:
Funder
National Natural Science Foundation of China
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering
Reference38 articles.
1. Materials challenges in nuclear energy;Zinkle;Acta Mater.,2013
2. Corrosion behavior of SA508 low alloy steels exposed to aerated boric acid solutions;Lim;Nucl. Eng. Technol.,2020
3. Crack growth and cracking behavior of Alloy 600/182 and Alloy 690/152 welds in simulated PWR primary water;Lim;Nucl. Eng. Technol.,2019
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1. Additive manufactured corrosion-resistant SS316L/IN625 functionally graded multi-material in hydrofluoric acid (HF) environment;Corrosion Science;2024-04
2. Potentiodynamic polarization analysis with various corrosion inhibitors on A508/IN-182/IN-52M/308L/316L welds;Kuwait Journal of Science;2024-04
3. Innovative prevention of stress corrosion crack propagation in nuclear power pipe welds;Materials Testing;2023-06-23
4. Dissimilar welding of austenitic and ferritic steels using nickel and stainless-steel filler: Associated issues;Proceedings of the Institution of Mechanical Engineers, Part E: Journal of Process Mechanical Engineering;2023-03-06
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