Evaluation of the interfacial shear strength and residual stress of TiAlN coating on ZIRLO™ fuel cladding using a modified shear-lag model approach
Author:
Funder
EPSRC
DOE-NEUP Integrated Research Project
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference33 articles.
1. Localized oxidation of zirconium alloys in high temperature and pressure oxidizing environments of nuclear reactors
2. Residual stresses and tetragonal phase fraction characterisation of corrosion tested Zircaloy-4 using energy dispersive synchrotron X-ray diffraction
3. TiN-based coatings on fuel cladding tubes for advanced nuclear reactors
4. Diffusion barrier properties of nitride-based coatings on fuel cladding
5. The in-reactor creep of cold-worked Zircaloy-2 and Zirconium-2.5 wt % niobium pressure tubes
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