Stress and temperature-dependent hydride reorientation of Zircaloy-4 cladding and its effect on the ductility degradation

Effects of hydride morphology on the embrittlement of Zircaloy-4 cladding

(2015) Ju-Seong Kim et al.   JOURNAL OF NUCLEAR MATERIALS

MAKING THE CASE FOR SAFE STORAGE OF USED NUCLEAR FUEL FOR EXTENDED PERIODS OF TIME: COMBINING NEAR-TERM EXPERIMENTS AND ANALYSES WITH LONGER-TERM CONFIRMATORY DEMONSTRATIONS

(2013) KEN B. SORENSON et al.   Nuclear Engineering and Technology

REVIEW OF SPENT FUEL INTEGRITY EVALUATION FOR DRY STORAGE

(2013) DONGHAK KOOK et al.   Nuclear Engineering and Technology

Ductile-to-brittle transition temperature for high-burnup cladding alloys exposed to simulated drying-storage conditions

(2012) M.C. Billone et al.   JOURNAL OF NUCLEAR MATERIALS

Ring Compression Ductility of High-Burnup Fuel Cladding after Exposure to Simulated LOCA Conditions

(2012) Fumihisa NAGASE et al.   JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY

Crack growth in the through-thickness direction of hydrided thin-wall Zircaloy sheet

(2011) Patrick A. Raynaud et al.   JOURNAL OF NUCLEAR MATERIALS

Hydride reorientation in Zircaloy-4 cladding

(2007) H.C. Chu et al.   JOURNAL OF NUCLEAR MATERIALS