Abstract
We will review tokamak divertor diagnostics currently in use to study issues relevant to next generation divertor design. The divertor represents perhaps the greatest technological challenge in the design of reactor tokamaks such as ITER, with designs currently requiring a reduction in heat flux to plasma facing surfaces obtained through radiative and charge exchange processes (i.e., the radiative divertor). Experiments to study these new divertor regimes and concepts require 2D profile measurements of the important plasma parameters, scrape-off-layer (SOL) and divertor plasma density and temperature, radiated power, impurity concentrations, particle sources, neutral pressure, and heat flux to surfaces. Diagnostics measurements in use on ASDEX-U, Alcator C-MOD, DIII-D, JET, and JT-60U include Langmuir probes, IRTV cameras, bolometer arrays, fast neutral pressure gauges, photodiode arrays, CCD cameras, and visible and VUV spectroscopy. Each diagnostic obtains unique information, but each also presents its own challenges of access and interpretation. For the future, ITER divertor diagnostics will require innovation to adapt to the long pulse, high power, and neutron environment.
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