Data for: Biaxial creep performance of CWSR Zircaloy-4 cladding at emulated off-normal conditions of interim dry storage facility
Published: 13 September 2018| Version 1 | DOI: 10.17632/gbb4xk277k.1
The processed data are provided to study the biaxial creep behavior of Zircaloy-4 cladding material with targeted hydrogen concentrations of 0 wppm, 300 wppm, and 750 wppm at 500°C and at effective stresses at mid-wall of 65 MPa, 55 MPa, and 40 MPa by using the pressurized tube technique. The effective creep strain at mid-wall is derived from the diameter strain of test. The strain-rate is derived from the effective creep strain. The stress exponent is evaluated based on the strain-rate.
Nuclear Energy, Zirconium Alloys, Creep, Zircaloy, Zirconium Hydride, Nuclear Fuel Storage