Study on Corrosion Model for Zr-1Sn-1Nb-0.3Fe Zirconium Alloy

Zhang Kun; Guo Xingkun; Liu Zhenhai; Xing Shuo; Chen Ping

doi:10.13832/j.jnpe.2015.S2.0093

Volume 36 Issue S2

Feb. 2025

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Article Navigation > Nuclear Power Engineering > 2015 > 36(S2): 93-96

Zhang Kun, Guo Xingkun, Liu Zhenhai, Xing Shuo, Chen Ping. Study on Corrosion Model for Zr-1Sn-1Nb-0.3Fe Zirconium Alloy[J]. Nuclear Power Engineering, 2015, 36(S2): 93-96. doi: 10.13832/j.jnpe.2015.S2.0093

Citation:

Zhang Kun, Guo Xingkun, Liu Zhenhai, Xing Shuo, Chen Ping. Study on Corrosion Model for Zr-1Sn-1Nb-0.3Fe Zirconium Alloy[J]. Nuclear Power Engineering, 2015, 36(S2): 93-96. doi: 10.13832/j.jnpe.2015.S2.0093

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Study on Corrosion Model for Zr-1Sn-1Nb-0.3Fe Zirconium Alloy

doi: 10.13832/j.jnpe.2015.S2.0093

Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China

Received Date: 2015-10-10
Rev Recd Date: 2015-11-20

Available Online: 2025-02-15

Abstract

Abstract

Cladding material is the focus in the fuel assembly design, and the main characteristics that limit the cladding material is its corrosion performance. The corrosion mechanisms in zirconium alloys is complicated, and the neutron irradiation condition causes uncertain effects on the corrosion of zirconium alloys, and thus, it is difficult to estimate the zirconium alloy corrosion behavior and build the corrosion model just based on the out-pile corrosion test. In this paper, the corrosion model is built for the first time by analyzing the in-pile corrosion test results for Zr-1Sn-1Nb-0.3Fe.
- Zr-1Sn-1Nb-0.3Fe zirconium alloy,
- Model building,
- Corrosion performance analysis