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Behavior mechanism and prediction models of stress corrosion cracking of stainless steels in pressurized water reactors

  • Pengfei Gao
  • , Yanhui Li
  • , Zhouyang Bai
  • , Shaoming Ding
  • , Yinan Zhang
  • , Limei Xing
  • , Zhihong Yu
  • Xi'an Jiaotong University
  • University of California at Berkeley

科研成果: 期刊稿件 › 文献综述 › 同行评审

6 引用 (Scopus)

摘要

Stress corrosion cracking (SCC) which has long been an essential topic for alloys exposed to subcritical water systems,is an urgent issue for pressurized water reactors (PWRs). Due to the complexity of the interaction of materials, environment, and stress, the SCC mechanism of consensus and the prediction model with mechanic extensibility are unavailable. Based on reviewing the typical characteristics and critical influence factors of SCC of stainless steels, this paper systematically summarizes, compares the more mainstream cracking mechanisms, and from the perspective of empirical and deterministic methods, discusses the applicable conditions of a series of SCC prediction models with high recognition via practical data, which are of great significance for strengthening readers’ understanding of SCC critical parameters and the matching service environment of each SCC mechanism, promoting the accurate prediction of SCC behavior and cumulative damage in the pressurized water reactors.

源语言英语
期刊论文编号113897
期刊Nuclear Engineering and Design
卷434
DOI
出版状态已出版 - 1 4月 2025

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