Cracking and spalling of the oxide layer developed in high-burnup Zircaloy-4 cladding under normal operating conditions in a PWR
Author:
Funder
U.S. Department of Energy
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference41 articles.
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4. Hydride embrittlement and irradiation effects on the hoop mechanical properties of pressurized water reactor (PWR) and boiling-water reactor (BWR) Zircaloy cladding tubes: Part III. Mechanical behavior of hydride in stress-relieved annealed and recrystall;Arsene;Metall. Mater. Trans.,2003
5. Pellet-clad interaction (PCI) failures of zirconium alloy fuel cladding—a review;Cox;J. Nucl. Mater.,1990
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