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

I. López-Galilea; Gerald Pintsuk; C. García-Rosales; Jochen Linke

doi:10.4028/www.scientific.net/AMR.59.288

Paper Titles

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

Compression Tests of High Strength Steels
p.293

Residual Stress Measurements in Mo/CuCrZr Tiles Using Neutron Diffraction
p.299

Nanoindentation and Micromechanical Testing of Iron-Chromium Alloys Implanted with Iron Ions
p.304

Role of Cr and Ti Contents on the Microstructure and Mechanical Properties of ODS Ferritic Steels
p.308

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

Abstract:

The technical design solution for the future thermonuclear fusion reactor, ITER, must guarantee a reasonable lifetime from a safety and economical point of view. Carbon fibre reinforced carbon (CFC) is envisaged as a corrective material solution for the strike point area of ITER divertor due to its high thermal shock resistance necessary to withstand excessive heat loads during transient thermal loads; in particular plasma disruptions that can deposit energy densities of several ten MJm-2 with a typical timescale in the order of milliseconds. In this work, as potential alternative to CFCs new finely dispersed TiC-doped isotropic graphites with high thermal conductivity and mechanical strength, manufactured using synthetic mesophase pitch “AR” as raw material, have been evaluated under typical disruption conditions using an energetic electron beam at the JUDITH facility.