In view of an efficient pulsed operation scenario of future nuclear fusion reactors, the effectiveness of a prompt and reliable plasma start-up is essential to improve plasma performance and reproducibility, especially after a disruptive event or to reduce dwell time between pulses. The foreseen solution to widen the operational window with respect to the pre-pulse conditions (background pressure and impurity content) is the use of Electron Cyclotron (EC) additional heating, which can compensate the radiation losses and sustain the plasma burn-trough phase. In order to design the operational scenario of future demonstrative reactors it is mandatory to set appropriate codes capable to extrapolate from present experiments the future scenarios. Experiments on TCV tokamak focused on discharge recovery by means of EC assisted start-up (82.7 GHz, XM2) have been carried out with toroidal electric field of 0.7 V/m, pressure before startup ranging between 2 and 10 mPa and neutral composition dominated by Ar impurity. Experimental results have been compared successfully with simulations provided by BKD0 code, which models in detail the burn-though phase and includes a consistent calculation of the EC absorbed power computed by the beam-tracing code GRAY in low density plasma and with a realistic description of the beam injection conditions, including polarization mix after beam reflection at the inner wall. The required additional power and impurity impact on startup has been determined for TCV and extrapolated to ITER, JT-60SA and DEMO. * See author list of 'S. Coda et al 2017 Nucl. Fusion 57 102011'

Discharge recovery by means of EC assisted start-up

D Ricci;G Granucci;D Farina;S Garavaglia;A Moro;
2018

Abstract

In view of an efficient pulsed operation scenario of future nuclear fusion reactors, the effectiveness of a prompt and reliable plasma start-up is essential to improve plasma performance and reproducibility, especially after a disruptive event or to reduce dwell time between pulses. The foreseen solution to widen the operational window with respect to the pre-pulse conditions (background pressure and impurity content) is the use of Electron Cyclotron (EC) additional heating, which can compensate the radiation losses and sustain the plasma burn-trough phase. In order to design the operational scenario of future demonstrative reactors it is mandatory to set appropriate codes capable to extrapolate from present experiments the future scenarios. Experiments on TCV tokamak focused on discharge recovery by means of EC assisted start-up (82.7 GHz, XM2) have been carried out with toroidal electric field of 0.7 V/m, pressure before startup ranging between 2 and 10 mPa and neutral composition dominated by Ar impurity. Experimental results have been compared successfully with simulations provided by BKD0 code, which models in detail the burn-though phase and includes a consistent calculation of the EC absorbed power computed by the beam-tracing code GRAY in low density plasma and with a realistic description of the beam injection conditions, including polarization mix after beam reflection at the inner wall. The required additional power and impurity impact on startup has been determined for TCV and extrapolated to ITER, JT-60SA and DEMO. * See author list of 'S. Coda et al 2017 Nucl. Fusion 57 102011'
2018
Istituto di fisica del plasma - IFP - Sede Milano
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/20.500.14243/372447
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