Assessment Method of Threshold Stress Intensity Factor of Delayed Hydride Cracking for Pressure Tube in Heavy Water Reactor

doi:10.11902/1005.4537.2024.221

Journal of Chinese Society for Corrosion and protection

2025, Vol. 45

Issue (2): 381-387 DOI: 10.11902/1005.4537.2024.221

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Assessment Method of Threshold Stress Intensity Factor of Delayed Hydride Cracking for Pressure Tube in Heavy Water Reactor

BAO Yichen¹, SHI Xiuqiang¹, MENG Fanjiang¹, PAN Chunting², MING Hongliang²(

)

^1.Shanghai Nuclear Engineering Research and Design Institute Co., Ltd., Shanghai 200233, China
^2.Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016, China

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BAO Yichen, SHI Xiuqiang, MENG Fanjiang, PAN Chunting, MING Hongliang. Assessment Method of Threshold Stress Intensity Factor of Delayed Hydride Cracking for Pressure Tube in Heavy Water Reactor. Journal of Chinese Society for Corrosion and protection, 2025, 45(2): 381-387.

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Abstract

The material properties of pressure tube will gradually deteriorate under high temperature, high pressure and high irradiation operating conditions of heavy water reactor (HWR), especially when the Zr-alloy absorbs deuterium/hydrogen from the coolant, it will become susceptive to the delayed hydride cracking (DHC), thus threatening the boundary integrity of the pressure tube. According to the Canadian Standard CSA N285.8, the threshold stress intensity factor (K_IH) for DHC needs to be evaluated. In response to this demand, the K_IH measurement method of pressure tube materials was studied. The K_IH was determined using compact tensile specimens, which were pre-charged with hydrogen by electrochemical method for about 180 mg/kg before tensile tests, and their K_IH values were measured at 250, 180, 150 and 120 ^oC respectively. The test results showed that the K_IH value of pressure tube Zr-2.5NbZr-alloy can be determined more accurately by using the K-reduction method at temperatures between 150 and 250 ^oC, and the measured values have no obvious dependence on the test temperatures.

Key words: pressure tube delayed hydride cracking threshold stress intensity factor heavy water reactor testing method

Received: 24 July 2024 32134.14.1005.4537.2024.221

TG172.1

Fund: National Key R&D Program(2019YFB1900902)

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

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https://www.jcscp.org/EN/10.11902/1005.4537.2024.221 OR https://www.jcscp.org/EN/Y2025/V45/I2/381

Fig.1 Schematic diagram of Zr-2.5Nb CCT specimen (a) and dimensions of CCT specimens (mm) (b)^[13]

Fig.2 Cross-sectional morphologies of axial-radial (a) and circumferential-radial (b)

Fig.3 Relationship between hydrogen charging duration and hydrogen concentration

Fig.4 Distribution of hydrides in the charged specimen

Table 1 Summary of effective potential increments and actual cracks length under different temperatures

Fig.5 Temperature and loading requirements for K_IH testing

Fig.6 Diagram of the calculation for fracture area

Fig.7 Loading history under different temperatures: (a) 250 ^oC, (b) 180 ^oC, (c) 150 ^oC, (d) 120 ^oC

Fig.8 Measured K_IH plot under different temperatures

Fig.9 Fracture morphologies under different temperatures: (a) 250 ^oC, (b) 180 ^oC, (c) 150 ^oC, (d) 120 ^oC

Fig.10 Fracture morphology observed at high magnification at 250 ^oC

Fig.11 Comparison of measured K_IH from K-increasing method and K-decreasing method^[8]

Fig.12 Effect of temperature on striation spacing of fracture surface^[13]

Fig.13 Relationship between increment upon TSSD and measured K_IH^[8]

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