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.

Compilation of erosion yields of metal-doped carbon materials by deuterium impact from ion beam and low temperature plasma

“…In conclusion, the optimized fine-grain graphite exhibits good enough thermo mechanical properties to withstand thermal loads, even those of off-normal events [14,15,16,17,18]. In addition, the achieved reduction of erosion leads to relaxation of problems of component lifetime, tritium retention in the material and co-deposited layers, and dust generation by flaking off of these layers.…”

“…In recent mock-up manufacturing and high heat flux (HHF) tests, the feasibility and reliability of the newly developed carbon-based materials and the corresponding joining technology to a Cu-based heat sink were shown [14,15,16,17,18]. Note that the properties of the tested materials cannot be found at present in any commercial graphite.…”