An evaluation of high-temperature creep of zirconium alloys: data versus models

Abstract

The steady-state creep data of as-received Zircaloy-4 and Zr-1wt%Nb used as fuel cladding materials in light water reactors, reported in the literature, have been reap- praised. The considered creep tests were conducted in the temperature range from 923 to 1873 K in inert environment covering all the solid-state zirconium alloy stable phase domains: α, (α + β) and β as a function of applied stress. The results of model cal- culations and measured data are compared, where the relative difference between the measured and calculated creep rate values are quantified for a series of tests. The mod- els considered are those used or can be used in predictive computer codes for fuel rod behaviour under loss-of-coolant accident conditions in light water reactors.