Microhardness and Young's modulus of high burn-up UO2 fuel

Author:

Cappia F.ORCID,Pizzocri D.,Marchetti M.,Schubert A.,Van Uffelen P.,Luzzi L.,Papaioannou D.,Macián-Juan R.,Rondinella V.V.

Funder

European Commission

Publisher

Elsevier BV

Subject

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

Reference57 articles.

1. 3.22-Modeling of pellet cladding interaction;Michel,2012

2. 3D thermo-chemical-mechanical simulation of power ramps with ALCYONE fuel code;Baurens;J. Nucl. Mater,2014

3. On the relations between the fission gas behaviour and the pellet-cladding mechanical interaction in LWR fuel rods;Van Uffelen,2004

4. Room-temperature microindentation behaviour of LWR-fuels, part 1: fuel microhardness;Spino;J. Nucl. Mater.,2003

5. Determination of high burn-up nuclear fuel elastic properties with acoustic microscopy;Laux;J. Nucl. Mater.,2012

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