Microcharacterization of Damage in Materials for Advanced Nuclear Fission Plants

Manuel A. Pouchon; Jia Chao Chen; W. Hoffelner

doi:10.4028/www.scientific.net/AMR.59.269

Paper Titles

Atomistic Simulation of ½<111> Screw Dislocations in BCC Tungsten
p.247

Ab-Initio Modelling of Point Defect-Impurity Interaction in Tungsten and other BCC Transition Metals
p.253

Characterization of MeV Ion-Irradiated SiC_f/SiC Composites Prepared with Different Methods
p.257

Numerical Simulation and Experimental Analysis of Laser Surface Remelting of AISI 420 Stainless Steel Samples
p.265

Microcharacterization of Damage in Materials for Advanced Nuclear Fission Plants
p.269

Preparation of Polymer-Nanodiamond Composites with Improved Properties
p.275

Microstructure and Properties of SiC Nanowire-Reinforced SiC_f/SiC Composites
p.279

Multi-Axial Thermo-Mechanical Fatigue of a Near-Gamma TiAl-Alloy
p.283

High Heat Flux Testing of TiC-Doped Isotropic Graphite for Plasma Facing Components
p.288

HomeAdvanced Materials ResearchAdvanced Materials Research Vol. 59Microcharacterization of Damage in Materials for...

Microcharacterization of Damage in Materials for Advanced Nuclear Fission Plants

Abstract:

Miniature and sub-miniature samples were used for determination of mechanical properties of materials for advanced fission plants. Results from indentation and focused ion beam prepared micro-samples, punch tests and thin strip (irradiation) creep tests are shown. The results allow conclusions concerning materials damage. Irradiation damage profiles were determined with indentation. Results from micro-pillar tests showed a good agreement with results from conventional samples in case of oxide dispersion strengthened steels. Thin strip irradiation creep experiments revealed a negligible influence of dispersoid size/distribution on creep rates. Punch tests of fibre reinforced materials showed consistent results which still need quantitative analysis.