Development of prediction model for stress corrosion cracking probability in scratched alloy 690TT heat transfer tubes

Author:

Li Rongbo,Wu Bin,Meng Fanjiang,Wang Haitao,Hou Dongcen,Ming Hongliang,Wang Jianqiu,Han En-Hou

Publisher

Elsevier BV

Reference30 articles.

1. Materials challenges in nuclear energy;Zinkle;Acta Mater,2013

2. 1 - Historical views on stress corrosion cracking of nickel-based alloys: The Coriou effect;Staehle,2016

3. Alloy optimization for PWR steam generator heat-transfer tubing;Harrod;JOM,2001

4. Nodular corrosion inside the crevice of Alloy 690 in deaerated high-temperature chloride solution;Ning;Corros. Sci.,2021

5. Muscara, design, Overview of steam generator tube degradation and integrity issues;Diercks;Nucl. Eng. Des.,1999

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