Analysis of tungsten migration from the C-MOD divertor; prediction of high redeposition rate, and code validation progress

For acceptable magnetic fusion reactor performance it is critical that net erosion of high-Z plasma facing material be much less than gross erosion. A detailed simulation of outer divertor-sputtered tungsten migration in the C-MOD tokamak, over an extended plasma campaign, shows a high ratio, ~×10, of gross/net erosion, no core plasma contamination, and moderate transport of tungsten to lower divertor regions. These code predictions agree well with the available data. This is encouraging for high-Z material use in ITER and future fusion devices.