Nanoindentation measurements of the mechanical properties of zirconium matrix and hydrides in unirradiated pre-hydrided nuclear fuel cladding

Author:

Rico A.,Martin-Rengel M.A.,Ruiz-Hervias J.,Rodriguez J.,Gomez-Sanchez F.J.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference27 articles.

1. Some observations on the deformation characteristics of bulk polycrystalline zirconium hydrides

2. A New Approach to Measuring Transverse Properties of Structural Tubing by a Ring Test

3. S. Arséne, Effet de la microstructure et de la temperature sur la transition ductile-fragile des zircaloy hydrures, Ph.D. dissertation, École Centrale Paris, 1997.

4. M.A. Martín-Rengel, Integridad estructural de vainas de combustible nuclear en condiciones de almacenamiento temporal en seco, Ph.D. Thesis, Universidad Politécnica de Madrid, 2009, in Spanish, ENRESA technical publication 05-2010. (in Spanish).

5. Revisiting the method to obtain the mechanical properties of hydrided fuel cladding in the hoop direction

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