Creep Tests Research on a New Zirconium Alloy for Nuclear Fuel Cladding Tubes

Xin Ming Meng; Fei Xue; Wei Wei Yu; Hong Mei Guo

doi:10.4028/www.scientific.net/AMM.151.47

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HomeApplied Mechanics and MaterialsApplied Mechanics and Materials Vol. 151Creep Tests Research on a New Zirconium Alloy for...

Creep Tests Research on a New Zirconium Alloy for Nuclear Fuel Cladding Tubes

Abstract:

Hoop creep tests and axial creep tests were carried out on a new zirconium alloy for nuclear fuel cladding tubes at 375 °C. The result indicated that the proportion of the second creep stage decreased as the stress increasing, meanwhile, the steady-state creep rate increased in both creep test modes. However, the ability of creep rupture resistance in the hoop direction is more strengthen than that in axial direction. The SEM analysis showed that the creep fracture was mainly dimple toughness fracture. The dimple for low stress was intensive and small. The fitting curve by the θ function was well coincided with the test data, so the creep life can be analyzed by θ function.

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Periodical:

Applied Mechanics and Materials (Volume 151)

Pages:

47-51

DOI:

https://doi.org/10.4028/www.scientific.net/AMM.151.47

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Online since:

January 2012

Authors:

Xin Ming Meng, Fei Xue, Wei Wei Yu, Hong Mei Guo

Keywords:

Creep, Nuclear Fuel, Zirconium Alloy

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