Effect of Neutron Irradiation on Mechanical Properties of Accident-Tolerant Fuel FeCrAl Alloys

Lei Yang; Zhang Haisheng; Mao Jianjun; Liu Xiaosong; Qiao Yingjie; Wang Peng; Wu Yazhen; Xiao Wenxia

doi:10.13832/j.jnpe.2022.01.0097

Volume 43 Issue 1

Feb. 2022

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Article Navigation > Nuclear Power Engineering > 2022 > 43(1): 97-101

Lei Yang, Zhang Haisheng, Mao Jianjun, Liu Xiaosong, Qiao Yingjie, Wang Peng, Wu Yazhen, Xiao Wenxia. Effect of Neutron Irradiation on Mechanical Properties of Accident-Tolerant Fuel FeCrAl Alloys[J]. Nuclear Power Engineering, 2022, 43(1): 97-101. doi: 10.13832/j.jnpe.2022.01.0097

Citation:

Lei Yang, Zhang Haisheng, Mao Jianjun, Liu Xiaosong, Qiao Yingjie, Wang Peng, Wu Yazhen, Xiao Wenxia. Effect of Neutron Irradiation on Mechanical Properties of Accident-Tolerant Fuel FeCrAl Alloys[J]. Nuclear Power Engineering, 2022, 43(1): 97-101. doi: 10.13832/j.jnpe.2022.01.0097

Citation:

Lei Yang, Zhang Haisheng, Mao Jianjun, Liu Xiaosong, Qiao Yingjie, Wang Peng, Wu Yazhen, Xiao Wenxia. Effect of Neutron Irradiation on Mechanical Properties of Accident-Tolerant Fuel FeCrAl Alloys[J]. Nuclear Power Engineering, 2022, 43(1): 97-101. doi: 10.13832/j.jnpe.2022.01.0097

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Effect of Neutron Irradiation on Mechanical Properties of Accident-Tolerant Fuel FeCrAl Alloys

doi: 10.13832/j.jnpe.2022.01.0097

1.
Nuclear Power Institute of China, Chengdu, 610213, China
2.
Harbin Engineering University, Harbin, 150001, China

Received Date: 2020-11-30
Rev Recd Date: 2021-01-07
Publish Date: 2022-02-01

Abstract

Abstract

FeCrAl alloy has good high-temperature oxidation resistance and mechanical properties and can be used as fuel cladding material. In order to study the irradiation mechanical properties of FeCrAl alloy, FeCrAl alloy mechanical properties test with different element contents and 2×10¹⁹ cm⁻² and 8×10¹⁹ cm⁻²neutron fluence irradiation was carried out, the tensile properties of FeCrAl alloys were tested at room temperature and 380℃, and the tensile strength and yield strength of FeCrAl alloys with different Cr and Al contents were obtained. The effects of Al content, Cr/Al content ratio and neutron irradiation on the mechanical properties of FeCrAl alloy were studied. The results show that the strength of FeCrAl alloy generally increases with the increase of Al content; After 2×10¹⁹ cm⁻² neutron irradiation, the strength of FeCrAl alloy is greatly improved; After 8×10¹⁹ cm⁻²neutron irradiation, the strength of FeCrAl alloy does not increase significantly. The research results provide important data support for the R&D and selection of accident-tolerant fuel cladding.
- FeCrAl alloy,
- Accident-tolerant fuel (ATF),
- Mechanical properties,
- Irradiation effect

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References(12)

References

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