X. Averty

发表

Behavior and failure of uniformly hydrided Zircaloy-4 fuel claddings between 25 °C and 480 °C under various stress states, including RIA loading conditions

Jacques Besson, S. Carassou, S. Carassou, 2010 .

The PROMETRA Program: Fuel Cladding Mechanical Behavior under High Strain Rate

Yann Monerie, J. Desquines, C. Bernaudat, 2007 .

Characterization of He embrittlement of a 9Cr–1Mo steel using local approach of brittle fracture

B. Marini, J. Henry, B. Marini, 2008 .

Comparative study on Charpy specimen reconstitution techniques

Y. Bienvenu, X. Averty, Y. Bienvenu, 2011 .

Mechanical Properties of Zircaloy-4 PWR Fuel Cladding with Burnup 54-64MWd/kgU and Implications for RIA Behavior

J. Desquines, C. Bernaudat, P. Yvon, 2005 .

Tensile and impact properties of 9Cr tempered martensitic steels and ODS-FeCr alloys irradiated in a fast reactor at 325 °C up to 78 dpa

A. Alamo, J. Henry, J. Henry, 2011 .

Tensile behaviour of 9Cr–1Mo tempered martensitic steels irradiated up to 20 dpa in a spallation environment

Y. Dai, J. Henry, Y. Dai, 2008 .