Abstract
Future magnetic-confinement devices which produce significant power by the fusion of D-T nuclei will require an adequate removal rate of helium ash from the plasma core, in order to maintain core purity and the level of power production1. Hence, the role of the divertor in removing helium is of crucial importance. At JET, several divertor configurations have been studied to characterise their efficacy at this task, under various operating conditions2.
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© 2002 Springer Science+Business Media New York
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Morgan, P.D. (2002). Helium Partial Pressure Measurements Using a Penning Gauge: A New Approach. In: Stott, P.E., Wootton, A., Gorini, G., Sindoni, E., Batani, D. (eds) Advanced Diagnostics for Magnetic and Inertial Fusion. Springer, Boston, MA. https://doi.org/10.1007/978-1-4419-8696-2_73
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DOI: https://doi.org/10.1007/978-1-4419-8696-2_73
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