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Helical Divertor System

Helical Divertor System
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Design optimization of the ITER tungsten divertor vertical targets

Fusion Engineering and Design, 2018
Gregory De Temmerman
exaly   +2 more sources

Resonant helical divertor

Physics Letters A, 1977
Abstract A concept for a helical divertor is proposed, which utilizes a resonance effect, and reduces the required divertor currents to a small fraction (typically 10 -2 ) of the plasma current. This divertor should have a larger screening efficiency than the poloidal field divertor, and could operate with divertor coils outside the vacuum vessel or ...
Karger, F., Lackner, K.
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ITER divertor materials and manufacturing challenges

Fusion Engineering and Design, 2017
T. Hirai, V. Barabash, F. Escourbiac, A. Durocher, L. Ferrand, V. Komarov, M. Merola   +6 more
exaly   +2 more sources

Kinetic divertor modeling

Chemical Physics, 2012
Abstract The coupled dynamics and kinetics between gas and plasma in the divertor region is studied by means of a one-dimensional Particle in Cell-Direct Simulation Monte Carlo (PIC-DSMC) model. In particular, the collision-induced vibrational excitation/relaxation of H2 molecules and particle–surface interaction (vibrational relaxation and ...
F Taccogna, P Minelli, D Bruno, S Longo, R Schneider   +4 more
openaire   +2 more sources

R.H. divertor maintenance – the divertor refurbishment platform

Fusion Engineering and Design, 2000
The ITER divertor assembly consists in 60 cassettes located in the bottom region of the vacuum vessel. Because of erosion and damage during, reactor operations, their replacement is expected to be required eight times during the machine lifetime. The cassettes will be withdrawn from the vessel through dedicated ducts and they will be transported to a ...
C Damiani, G Bertacci, M Irving, M Armeni, G Collina, L Baldi, L Muro, G Varocchi, A Poggianti, G Cerdan, D Maisonnier, J Palmer, S Chiocchio, M Siuko, A Turner   +14 more
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Assessment of ITER divertor performance during early operation phases

Nuclear Fusion, 2020
During the ITER design phase, the focus of ITER boundary plasma modeling activities has been on divertor performance under baseline H-mode, fusion power operation (FPO) conditions.
Jae-Sun Park, X. Bonnin, R. Pitts
semanticscholar   +1 more source

R.H. divertor maintenance — the divertor test platform

Fusion Engineering and Design, 2000
The ITER divertor assembly consists in 60 cassettes located in the bottom region of the vacuum vessel. Because of erosion and damage, their replacement is expected to be required eight times during the machine lifetime. The cassettes will be remotely withdrawn from the vessel through dedicated ducts and they will be transported to a hot cell for ...
C Damiani, L Lorenzelli, L Baldi, G Miccichè, L Muro, S Nucci, S Panichi, G Pierucci, G Varocchi, P.A Gaggini, G Fermani, G Cerdan, D Maisonnier, E Martin, E Tada, N Takeda   +15 more
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Divertor parameters and divertor operation in ASDEX

Journal of Nuclear Materials, 1984
Abstract Recent measurements of plasma boundary and divertor scrape-off parameters for ohmically and neutral injection heated plasmas are presented. For these data the power flow onto the divertor plates and the sputtering rates at the plates are calculated and compared with separate measurements. The impurity behaviour in front of the plates is also
Fussmann, G., et al.
exaly   +4 more sources

The ITER divertor concept

Journal of Nuclear Materials, 1995
Abstract The ITER divertor must exhaust most of the alpha particle power and the He ash at acceptable erosion rates. The high recycling regime of the ITER-CDA for present parameters would yield high power loads and erosion rates on conventional targets. Improvement by radiation in the SOL at constant pressure is limited in principle.
Janeschitz, G., Borras, K., Federici, G., Igitkhanov, Y., Kukushkin, A., Pacher, H., Pacher, G., Sugihara, M.   +7 more
openaire   +2 more sources