重水堆压力管延迟氢化物开裂行为研究进展

doi:10.11902/1005.4537.2024.157

中国腐蚀与防护学报

2025, Vol. 45

Issue (2): 307-318 CSTR: 32134.14.1005.4537.2024.157 DOI: 10.11902/1005.4537.2024.157

临氢关键材料服役行为研究专刊

本期目录 | 过刊浏览

重水堆压力管延迟氢化物开裂行为研究进展

潘春婷¹^,², 明洪亮¹^,²(

), 石秀强³, 鲍一晨³, 王俭秋¹^,²^,⁴, 韩恩厚²^,⁴

^1.中国科学技术大学材料科学与工程学院沈阳 110016
^2.中国科学院金属研究所沈阳 110016
^3.上海核工程研究设计院股份有限公司上海 200233
^4.广东腐蚀科学与技术创新研究院广州 510530

Research Progress on Delayed Hydrides Cracking Behavior of Heavy Water-Reactor Pressure Tube

PAN Chunting¹^,², MING Hongliang¹^,²(

), SHI Xiuqiang³, BAO Yichen³, WANG Jianqiu¹^,²^,⁴, HAN En-Hou²^,⁴

^1.School of Materials of Science and Engineering, University of Science and Technology of China, Shenyang 110016, China
^2.Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016, China
^3.Shanghai Nuclear engineering Research and Design Institute Co., Ltd., Shanghai 200233, China
^4.Institute of Corrosion Science and Technology, Guangzhou 510530, China

引用本文:

潘春婷, 明洪亮, 石秀强, 鲍一晨, 王俭秋, 韩恩厚. 重水堆压力管延迟氢化物开裂行为研究进展[J]. 中国腐蚀与防护学报, 2025, 45(2): 307-318.
Chunting PAN, Hongliang MING, Xiuqiang SHI, Yichen BAO, Jianqiu WANG, En-Hou HAN. Research Progress on Delayed Hydrides Cracking Behavior of Heavy Water-Reactor Pressure Tube[J]. Journal of Chinese Society for Corrosion and protection, 2025, 45(2): 307-318.

全文: PDF(2070 KB) HTML

摘要:

压力管是重水堆中重要的结构部件，其服役性能是确保重水堆安全稳定运行的关键。延迟氢化物开裂(DHC)是压力管服役过程中最重要的潜在风险之一，因此研究压力管的DHC行为具有重要的意义。本文就DHC行为测试的实验方法、机理和模型以及DHC行为的影响因素等方面的研究进展进行综述，并指出目前研究存在的不足和未来的发展趋势。

关键词 ：重水堆, 压力管, Zr-2.5Nb合金, 延迟氢化物开裂

Abstract：

Zr-2.5Nb alloy pressure tubes are important structural components in heavy-water reactor. During operation of a heavy-water reactor, a large amount of hydrogen isotopes is produced by the corrosion reaction between the pressure tubes and the heavy-water coolant. Some of the hydrogen isotopes can be absorbed into the pressure tube. When the concentration of hydrogen atoms exceeds the solid solubility of hydrogen in Zr-2.5Nb alloy, hydrides are precipitated. The precipitation of hydrides will lead to deterioration of mechanical properties of Zr-2.5Nb alloy, and then leads to the expansion of microcracks inside the pressure tubes. The phenomenon is called Delayed hydrides cracking (DHC) which is one of the most important potential risks during the service of pressure tubes. Therefore, it is of great significance to study the DHC behavior of pressure tube. In this paper, the research progress on the testing methods for DHC behavior, the relevant mechanisms and models as well as the influencing factors of DHC behavior are reviewed, and the shortcomings of current researches and the future development trends are pointed out.

Key words： heavy-water reactor pressure tubes Zr-2.5Nb alloy delayed hydrides cracking

收稿日期: 2024-05-18 32134.14.1005.4537.2024.157

ZTFLH:

TG174

基金资助:中国科学院青年创新促进会(2022187)

通讯作者: 明洪亮，E-mail：hlming12s@imr.ac.cn，研究方向为材料力学化学交互作用

Corresponding author: MING Hongliang, E-mail: hlming12s@imr.ac.cn

作者简介: 潘春婷，女，1997年生，博士生

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https://www.jcscp.org/CN/10.11902/1005.4537.2024.157 或 https://www.jcscp.org/CN/Y2025/V45/I2/307

图1 试样取样及尺寸示意图

图2 试样加载示意图

图3 DHCR随KI变化规律[19]

图4 锆合金TSSP及TSSD汇总图[35]

图5 DHC裂纹扩展过程示意图[40]

图6 基于TSS曲线的热循环过程中氢含量变化示意图[36]

图7 裂纹尖端静水应力分布和稳态扩散条件下裂纹尖端氢浓度分布示意图[46]

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