Thermal isocreep curves obtained during multi-axial creep tests on recrystallized Zircaloy-4 and M5™ alloy - Archive ouverte HAL Access content directly
Journal Articles Nuclear Engineering and Design Year : 2014

Thermal isocreep curves obtained during multi-axial creep tests on recrystallized Zircaloy-4 and M5™ alloy

Abstract

Zirconium alloys are widely used in the nuclear industry. Several components, such as cladding or guide tubes, undergo strong mechanical loading during and after their use inside the pressurized water reactors. The current requirements on higher fuel performances lead to the developing on new Zr based alloys exhibiting better mechanical properties. In this framework, creep behaviors of recrystallized Zircaloy-4 and M5™, have been investigated and then compared. In order to give a better understanding of the thermal creep anisotropy of Zr-based alloys, multi-axial creep tests have been carried out at 673K. Using a specific device, creep conditions have been set using different values of β=σzz/σθθ, σzz and σθθ being respectively the axial and hoop creep stresses. Both axial and hoop strains are measured during each test which is carried out until stationary creep is stabilized. The steady-state strain rates are then used to build isocreep curves. Considering the isocreep curves, the M5™ alloy shows a largely improved creep resistance compared to the recrystallized Zircaloy-4, especially for tubes under high hoop loadings (0<β<1). The isocreep curves are then compared with simulations performed using two different mechanical models. Model 1 uses a von Mises yield criterion, the model 2 is based on a Hill yield criterion. For both models, a coefficient derived from Norton law is used to assess the stress dependence.

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Materials
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Dates and versions

hal-01011653 , version 1 (05-02-2019)

Identifiers

Cite

Martin Rautenberg, Dominique Poquillon, Philippe Pilvin, C. Grosjean, J.M. Cloue, et al.. Thermal isocreep curves obtained during multi-axial creep tests on recrystallized Zircaloy-4 and M5™ alloy. Nuclear Engineering and Design, 2014, 269, pp.33-37. ⟨10.1016/j.nucengdes.2013.08.002⟩. ⟨hal-01011653⟩
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