Feasibility of an MSE system on the TCV tokamak
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This paper presents a feasibility study for a MSE diagnostic on the TCV tokamak. A numerical simulation code has been used to identify the optimal port arrangement and geometrical layout. It predicts the expected measurement accuracy for a range of typical plasma scenarios. With the existing Neutral Particle Injector and a detection system based on current day technology, it should be possible to determine the safety factor with an accuracy of the order of 5%. A vertically injected beam through the plasma center would allow to measure plasmas which are centered above the midplane, a common occurrence in connection with ECRH/ECCD experiments. In this case a new and ideally more powerful NBI would be required.
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