Evaluation on I-SCC Properties of Zirconium Cladding

Yan Meng; Wang Pengfei; Hong Xiaofeng; Liang Bo; DAi Xun

doi:10.13832/j.jnpe.2017.05.0138

Volume 38 Issue 5

Feb. 2025

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Yan Meng, Wang Pengfei, Hong Xiaofeng, Liang Bo, DAi Xun. Evaluation on I-SCC Properties of Zirconium Cladding[J]. Nuclear Power Engineering, 2017, 38(5): 138-140. doi: 10.13832/j.jnpe.2017.05.0138

Citation:

Yan Meng, Wang Pengfei, Hong Xiaofeng, Liang Bo, DAi Xun. Evaluation on I-SCC Properties of Zirconium Cladding[J]. Nuclear Power Engineering, 2017, 38(5): 138-140. doi: 10.13832/j.jnpe.2017.05.0138

Yan Meng, Wang Pengfei, Hong Xiaofeng, Liang Bo, DAi Xun. Evaluation on I-SCC Properties of Zirconium Cladding[J]. Nuclear Power Engineering, 2017, 38(5): 138-140. doi: 10.13832/j.jnpe.2017.05.0138

Citation:

Yan Meng, Wang Pengfei, Hong Xiaofeng, Liang Bo, DAi Xun. Evaluation on I-SCC Properties of Zirconium Cladding[J]. Nuclear Power Engineering, 2017, 38(5): 138-140. doi: 10.13832/j.jnpe.2017.05.0138

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Evaluation on I-SCC Properties of Zirconium Cladding

doi: 10.13832/j.jnpe.2017.05.0138

Science and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China

Received Date: 2017-03-09
Rev Recd Date: 2017-04-27

Available Online: 2025-02-09

Abstract

Abstract

Hoop tensile test were performed on zirconium（such as N36, Zr-4 and X） ring specimens at 350℃ and 400℃ to study the iodine induced stress corrosion cracking（I-SCC） behavior of zirconium cladding in 10~2 Pa, 10~3 Pa and 10~4 Pa iodine partial pressure environment. Different levels of I-SCC happened with N36, Zr-4 and X samples at special iodine partial pressure with the maximum load, and the fracture energy dropped down quickly as result, and N36 maximum load and fracture energy dropped slower at same test situation.
- Iodine induced stress corrosion cracking（I-SCC）,
- Zirconium cladding,
- Hoop tensile