Experimental Study on Low-Cycle Fatigue Properties of Supercritical Water-cooled Reactor Candidate Cladding Material

Zhao Yuxiang; Xiong Ru; Liang Bo; Tang Rui

doi:10.13832/j.jnpe.2023.05.0237

Volume 44 Issue 5

Oct. 2023

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Zhao Yuxiang, Xiong Ru, Liang Bo, Tang Rui. Experimental Study on Low-Cycle Fatigue Properties of Supercritical Water-cooled Reactor Candidate Cladding Material[J]. Nuclear Power Engineering, 2023, 44(5): 237-243. doi: 10.13832/j.jnpe.2023.05.0237

Citation:

Zhao Yuxiang, Xiong Ru, Liang Bo, Tang Rui. Experimental Study on Low-Cycle Fatigue Properties of Supercritical Water-cooled Reactor Candidate Cladding Material[J]. Nuclear Power Engineering, 2023, 44(5): 237-243. doi: 10.13832/j.jnpe.2023.05.0237

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Experimental Study on Low-Cycle Fatigue Properties of Supercritical Water-cooled Reactor Candidate Cladding Material

doi: 10.13832/j.jnpe.2023.05.0237

Zhao Yuxiang^{1, 2
,},
Xiong Ru¹,
Liang Bo¹,
Tang Rui¹

1.
Science and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China
2.
Polymer Research Institute, Sichuan University, Chengdu, 610065, China

Received Date: 2022-12-05
Rev Recd Date: 2023-01-12
Publish Date: 2023-10-13

Abstract

Abstract

In order to obtain the low cycle fatigue performance data of 20Cr-25Ni, a candidate cladding material for supercritical water cooled reactor (SCWR), and to provide technical reference for the design, development and engineering of SCWR, the low cycle fatigue tests of 20Cr-25Ni at room temperature, 500℃, 650℃ and 800℃ were carried out on MTS809 testing machine, and the multi-level cyclic hysteresis curve, cyclic stress-strain curve, the relationship curve between stress amplitude and cyclic fraction, cyclic stress-strain model and low cycle fatigue Manson-Coffin model parameters were obtained. The results of low cycle fatigue test of 20Cr-25Ni show that the fatigue resistance of 20Cr-25Ni stainless steel pipe decreases with the increase of temperature, and shows obvious cyclic hardening at 500℃ and 650℃. Therefore, the cladding material has good fatigue resistance below 650℃. When the maximum core temperature of SCWR is higher than 650℃, it is necessary to be careful to use this material as cladding material.
- Supercritical water-cooled reactor (SCWR),
- Cladding tube,
- Stainless steel,
- Low cycle fatigue,
- Curve

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References(9)

References

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