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Motional Stark effect produces large net linear polarization of hydrogenic beam emissions. Measurement of the polarization direction permits to determine the local magnetic field pitch angle. Design of a single point, spatially scannable, high-sensitivity polarimeter installed on DIII-D is described. Excellent signal-to-noise ratio with good temporal and spatial resolution was obtained in preliminary measurements of magnetic field pitch angle. 9 refs., 3 figs.
The advanced tokamak research program at DIII-D relies critically on the measurement of the current density profile. This was made possible by the development of a Motional Stark Effect (MSE) polarimeter that was first installed in 1992. Three major upgrades have since occurred, and improvements in our understanding of critical performance issues and calibration techniques are ongoing. In parallel with these improvements, we have drawn on our DIII-D experience to begin studies and design work for MSE on burning plasmas and ITER. This paper first reviews how Motional Stark Effect polarimetry (MSE) is used to determine the tokamak current profile. It uses the DIII-D MSE system as an example, and shows results from the latest upgrade that incorporates an array of channels from a new counter-Ip injected neutral beam. The various calibration techniques presently used are reviewed. High-leverage or unresolved issues affecting MSE performance and reliability in ITER are discussed. Next, we show a four-mirror collection optics design for the two ITER MSE views. Finally, we discuss measurements of the polarization properties of a few candidate mirrors for the ITER MSE.
Proceedings of the International Conference on Advanced Diagnostics for Magnetic and Inertial Fusion, held September 3-7, 2001 at Villa Monastero, Varenna, Italy. This volume focuses on future diagnostic requirements for fusion energy research emphasizing advanced diagnostics, new techniques and areas where further progress is required.
ITER (the International Thermonuclear Experimental Reactor, a joint venture between Europe, Japan, Russia, USA, China, India and South Korea) will need to measure a wide range of plasma parameters in order to reach and sustain high levels of fusion power and provide input to control systems with adequate reliability and long-term stability. The conference was the first appointment of the diagnostic community after the approval of ITER, and was therefore an opportunity to review the status of ITER diagnostics with particular reference to the capabilities of the present proposed systems to meet the requirements on the measurements. Critical issues related with the measurements of fast particles, fusion products, plasma facing components and radiation effects were addressed as well as new areas of diagnostic developments related with DEMO, the next step fusion reactor that will deliver electrical power from fusion.
The measurement and control of the plasma current density profile (or q profile) is critical to the advanced tokamak program on DIII-D.A complete understanding of the stability and transport properties of advanced operating regimes requires detail poloidal field measurements over the entire plasma radius from the core to the edge. In support of this effort, the authors have recently completed an upgrade of the existing MSE diagnostic, increasing the number of channels from 8 to 16. A new viewing geometry has been added to the outer edge of the plasma which improves the radial resolution in this region from 10 cm to
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