SOME CORROSION PROBLEMS OF ALLOY 690TT IN SPECIAL ENVIRONMENTS

J Chin Soc Corr Pro

2010, Vol. 30

Issue (3): 251-256 DOI:

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SOME CORROSION PROBLEMS OF ALLOY 690TT IN SPECIAL ENVIRONMENTS

YU Yuanfang, WANG Hui, HU Shilin

China Institute of Atomic Energy, Beijing 102413

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Abstract

In order to improve the reliability of PWR steam generators, alloy 690TT has been developed and verified as the optimum steam generators (SGs) tubing material at present, based on wide operating and laboratorial experience. Alloy 690TT is and will be one of most popular tube material of present and future commercial nuclear plants. Alloy 690TT is usually insusceptible both under acidic and alkaline conditions, but the corrosion is unavoidable under special corrosive environment in time. Dealloying (Cr depletion), lead stress corrosion cracking (PbSCC), low-valence sulfur stress corrosion cracking (S^y-CC) are considered being potential damage to Alloy 690TT and will be described in detail in this article.

Key words: steam generator alloy 690TT lead stress corrosion cracking (PbSCC) dealloying low-valence sulfur stress corrosion cracking (S^y-CC)

Received: 16 February 2009

ZTFLH:

TG172.9

Corresponding Authors: YU Yuanfang E-mail: yuyuanf@126.com

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Cite this article:

YU Yuanfang, WANG Hui, HU Shilin. SOME CORROSION PROBLEMS OF ALLOY 690TT IN SPECIAL ENVIRONMENTS. J Chin Soc Corr Pro, 2010, 30(3): 251-256.

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https://www.jcscp.org/EN/ OR https://www.jcscp.org/EN/Y2010/V30/I3/251

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