1-1 of 1
Keywords: fission reactor fuel claddings
Close
Save search
Follow your search
Access your saved searches in your account
Would you like to receive an alert when new items match your search?
Close Modal
Sort by
Journal Articles

Thermomechanical Behavior and Modeling Between 350°C and 400°C of Zircaloy-4 Cladding Tubes From an Unirradiated State to High Fluence (0 to 85 s ˙ 10 24   nm − 2 , E > 1   MeV )

I. Scha¨ffler, P. Geyer, P. Bouffioux, P. Delobelle
Journal: Journal of Engineering Materials and Technology
Publisher: ASME
Article Type: Technical Papers
J. Eng. Mater. Technol. April 2000, 122(2): 168–176.
https://doi.org/10.1115/1.482783
Published Online: July 6, 1999
..., 1998; revised manuscript received July 6, 1999. Associate Technical Editor: Kwai S. Chan. 12 November 1998 06 July 1999 fission reactor fuel claddings zirconium alloys neutron effects work hardening stress relaxation radiation hardening creep viscoplasticity Today...
View Article titled, Thermomechanical Behavior and Modeling Between 350°C and 400°C of Zircaloy-4 Cladding Tubes From an Unirradiated State to High Fluence (0 to 85 s ˙ 10 24   nm − 2 , E > 1   MeV )
Open the PDF for Thermomechanical Behavior and Modeling Between 350°C and 400°C of Zircaloy-4 Cladding Tubes From an Unirradiated State to High Fluence (0 to 85 s ˙ 10 24   nm − 2 , E > 1   MeV ) in another window
Topics: Cladding systems (Building), Creep, Fluence (Radiation measurement), Irradiation (Radiation exposure), Modeling, Stress, Temperature, Hardening, Work hardening, Relaxation (Physics)