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Journal of Chinese Society for Corrosion and protection  2025, Vol. 45 Issue (2): 307-318    DOI: 10.11902/1005.4537.2024.157
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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
Cite this article: 

PAN Chunting, MING Hongliang, SHI Xiuqiang, BAO Yichen, WANG Jianqiu, HAN En-Hou. Research Progress on Delayed Hydrides Cracking Behavior of Heavy Water-Reactor Pressure Tube. Journal of Chinese Society for Corrosion and protection, 2025, 45(2): 307-318.

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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     
Received:  18 May 2024      32134.14.1005.4537.2024.157
:  TG174  
Fund: Youth Innovation Promotion Association CAS(2022187)
Corresponding Authors:  MING Hongliang, E-mail: hlming12s@imr.ac.cn
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PAN Chunting
MING Hongliang
SHI Xiuqiang
BAO Yichen
WANG Jianqiu
HAN En-Hou

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https://www.jcscp.org/EN/10.11902/1005.4537.2024.157     OR     https://www.jcscp.org/EN/Y2025/V45/I2/307

Fig.1  Schematic diagrams of sampling (a) and dimensions of CCT specimen (b) and CB specimen (c). B is thickness of pressure tube in Fig.1b and 1c, the unit is mm
Fig.2  Schematic diagrams of loading for CB specimen (a) and CCT specimen (b). F is the external load
Fig.3  Influence of KI on DHCR[19]. KIH is the threshold of stress intensity factor for DHC, KIC is the fracture toughness
Fig.4  Summary of TSSP and TSSD for Zirconium and its alloys[35]
Fig.5  Diagrams of the propagation of cracks during DHC[40]
Fig.6  Variations of hydrogen concentration with temperature during thermal cycling, obtained based on TSS curves[36]
Fig.7  Stress distribution at the crack tip (a) and hydrogen concentration distribution at the crack tip under steady state diffusion condition (b)[46]
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