|About this Abstract
||2016 TMS Annual Meeting & Exhibition
||Materials and Fuels for the Current and Advanced Nuclear Reactors V
||AA-1: Influence of Zirconium Hydride on the Biaxial Thermal Creep Behavior of Zircaloy-4 Cladding at 573 K and 773 K
||Kuan-Che Lan, Hsiao-Ming Tung, Yinbin Miao, Xiang Liu, Giuseppe Brunetti, Huan Yan, Di Yun, Kun Mo, James F. Stubbins
|On-Site Speaker (Planned)
Low temperature creep rupture of high burnup nuclear used fuel (UNF) (>45 GWD/MTU) cladding is a possible failure mechanism during long-term dry storage. In this study, the pressurized tube technique was employed to test the durability of as-hydrided Zircaloy-4 tubular specimens with 300 and 750 wt ppm hydrogen, and the influence of zirconium hydride on the biaxial thermal creep behavior of Zircaloy-4 cladding. Test temperatures and effective stresses at mid-wall of cladding ranged from 573 to 773 K, and from 40 to 65 MPa, respectively. Creep strain was obtained by measuring the diameter strain at various exposure times. Ex-situ synchrotron wide–angle x-ray scattering (WAXS) tests were used to investigate the dominant creep mechanism under possible dry storage conditions. The goal of this study is to develop a better understanding of materials performance to support the design basis of interim and long-term dry storage facilities for up to 300 years.
||Planned: A print-only volume