Mechanical behavior of long-term neutron-irradiated Al-Mg-Si alloy under compression

HU Ling; ZHENG Hang; FENG Qijie; ZHOU Wei; YE Xiangping; LU Lei

doi:10.11883/bzycj-2018-0483

Volume 39 Issue 12

Dec. 2019

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HU Ling, ZHENG Hang, FENG Qijie, ZHOU Wei, YE Xiangping, LU Lei. Mechanical behavior of long-term neutron-irradiated Al-Mg-Si alloy under compression[J]. Explosion And Shock Waves, 2019, 39(12): 123101. doi: 10.11883/bzycj-2018-0483

Citation:

HU Ling, ZHENG Hang, FENG Qijie, ZHOU Wei, YE Xiangping, LU Lei. Mechanical behavior of long-term neutron-irradiated Al-Mg-Si alloy under compression[J]. Explosion And Shock Waves, 2019, 39(12): 123101. doi: 10.11883/bzycj-2018-0483

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Mechanical behavior of long-term neutron-irradiated Al-Mg-Si alloy under compression

doi: 10.11883/bzycj-2018-0483

1.
National Key Laboratory of Shock Wave and Detonation Physics, Institute of Fluid Physics, CAEP, Mianyang 621999, Sichuan, China
2.
Key Laboratory of Mechanical Behavior and Design of Materials, CAS, Department of Modern Mechanics, University of Science and Technology of China, Hefei 230027, Anhui,China
3.
Institute of Nuclear Physics and Chemistry, CAEP, Mianyang 621999, Sichuan, China
4.
Key Laboratory of Advanced Technologies of Materials, Ministry of Education, Southwest Jiaotong University, Chengdu 610031, Sichuan, China

Received Date: 2018-11-30
Rev Recd Date: 2019-05-24

Available Online: 2019-11-25

Publish Date: 2019-12-01

Abstract

Abstract

The mechanical behavior of Al-Mg-Si alloy after long-term neutron irradiation (i.e. LT21 aluminum alloy served in the reactor for nearly 30 years) under compression loading with different temperature and strain rates is experimentally studied using material test system and split Hopkinson pressure bar. The effects of temperature and strain rate on its yield strength and flow stress are obtained. The results show that the material exhibits obvious temperature effect within a temperature rang from −40 ℃ to 300 ℃ and positive strain rate effect in a strain rate rang from 0.001 to 3 000 s⁻¹, respectively. At a lower temperature range (from −80 to −40 ℃) and higher strain rates (from 3 000 to 5 000 s⁻¹), the mechanical properties are insensitive to changes in temperature and strain rate. When the temperature reaches 300 ℃, the plastic deformation behavior of the material tends to ideal plastic flow. Based on the above experimental results, a modified Zerilli-Armstrong constitutive model considering irradiation damage is established by taking into account the effect of microscale irradiation defects on the mechanical properties of materials. The Zerilli-Armstrong model predictions are in good agreement with the experimental results. Furthermore, the yield strength of LT21 aluminum alloy with different fast neutron irradiation doses and the yield strength of another two samples obtained from different irradiated regions within the reactor at different strain rates and temperature are calculated by reference to the evolution of microscale irradiation defects of high purity aluminum. The above research shows that the Zerilli-Armstrong constitutive equation considering radiation damage established in this paper can not only establish the relationship between macroscale stress and strain, strain rate and temperature of the Al-Mg-Si alloy after long-term neutron irradiation, but also describe the dislocation motion and the mechanism of irradiation hardening. It can provide reference for the design, operation and safety evaluation of the corresponding structural elements in the nuclear reactor.
- impact dynamics,
- irradiation damage,
- Zerilli-Armstrong constitutive model,
- SHPB,
- neutron-irradiated Al-Mg-Si alloy

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References(20)

References

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