J. Mater. Sci. Technol. ›› 2025, Vol. 220: 1-13.DOI: 10.1016/j.jmst.2024.09.011

• Research Article •     Next Articles

Effect of polyacrylic acid on the corrosion behavior of Alloy 690 in pressurized water reactor secondary water

Zhiyuan Zhanga,b,c, Zhiming Zhangc, Jianqiu Wanga,b,c,*, Hongliang Minga,b, Haipeng Zhua,b,c, Tichun Dand, Ruoyu Wangc, Beibei Gaoc, En-Hou Hana,c,e   

  1. aCAS Key Laboratory of Nuclear Materials and Safety Assessment, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016, China;
    bSchool of Materials Science and Engineering, University of Science and Technology of China, Shenyang 110016, China;
    cInstitute of Corrosion Science and Technology, Guangzhou 510530, China;
    dChina Nuclear Power Operation Technology Corporation Co., Ltd., China National Nuclear Corporation, Wuhan 430223, China;
    eSchool of Materials Science and Engineering, South China University of Technology, Guangzhou 510006, China
  • Received:2024-07-11 Revised:2024-08-14 Accepted:2024-09-02 Published:2025-06-10 Online:2025-06-17
  • Contact: *E-mail address: wangjianqiu@imr.ac.cn (J. Wang)

Abstract: The effect of polyacrylic acid (PAA) on the corrosion behavior of Alloy 690 in simulated pressurized water reactor secondary water was investigated. The duplex oxide film structure, consisting of a Ni-rich outer layer and a Cr-rich inner layer, was maintained regardless of PAA presence. PAA inhibited the growth of outer Ni-rich particles while promoting Cr enrichment in the inner layer and inducing its amorphization, both enhancing oxidation resistance. However, excess PAA (≥ 500 ppb) suppressed protective oxide formation during initial oxidation, leading to oxygen penetration into the matrix. A PAA concentration of around 250 ppb is considered optimal for steam generators, as it provides the benefits of PAA without adverse effects on the alloy.

Key words: Polyacrylic acid, Alloy 690, Pressurized water reactor, Secondary water, Oxide film