Abstract
Neutron diagnose in deuterium-tritium (D-T) plasmas1 results increasingly important as these become hotter and more dense because other more conventional techniques will experience difficulties, due to the increasing plasma opacity and to the radiation damage to the instrumentation. In addition, neutron measurements could provide the only direct way to observe fusion reactivity. They have been already used in the D-T phase of the JET2 and the TFTR3 tokamaks, deducing from them the total fusion power and the ion temperature. In the ITER conceptual design4 (CDA) neutron detection systems are candidates for determination of plasma position and shape, fusion power, ion temperature, D/T density and disruption precursors.
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