Nuclear Fusion · 2023 · 14 citations · 84 references
Natural SciencesNuclear EngineeringPhysicsFusion EngineeringNuclear PhysicsPlasma PhysicsFusion PlasmasHigh-temperature PlasmasMagnetic Confinement FusionNuclear FusionPlasma ConfinementPlasma DiagnosticsDivertor MaterialsDivertor PhysicsHelium EmbrittlementPlasma Facing ComponentsPlasma Transport ProcessesPlasma-facing MaterialsTokamak PhysicsTokamak Plasmas
Abstract An efficient removal of He ash by active pumping in future fusion devices is necessary to avoid fuel dilution and not degrade the core confinement properties. Therefore, a deep understanding of the underlying physics mechanisms is mandatory. Helium exhaust has been experimentally investigated at the ASDEX Upgrade tokamak. This is an ideal test environment, thanks to the ITER-like divertor geometry, an extensive diagnostics coverage and the presence of plasma-facing components made of tungsten. The exhaust efficiency, characterized by the He compression in the divertor, was found to improve with increasing divertor neutral pressure but to degrade with detachment. A multi-reservoir particle balance model was developed to interpret the observed exhaust dynamics, accounting for plasma transport and wall retention. The limited performance of the pumping system and the efficient helium retention capability of the tungsten wall were identified to have the strongest impact on the exhaust dynamics.
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Chapter 4: Power and particle control
A. Loarte, B. Lipschultz, A.S. Kukushkin et al. · Nuclear Fusion · 2007 · 1.1K citations · Full text
Sputtering studies with the Monte Carlo Program TRIM.SP
J.P. Biersack, W. Eckstein · Applied Physics A · 1984 · 916 citations
Integrated Data Analysis of Profile Diagnostics at ASDEX Upgrade
R. Fischer, C. Fuchs, B. Kurzan et al. · Fusion Science & Technology · 2010 · 268 citations
Natural Sciences, Nuclear Engineering, Bayesian Data Analysis +12