Results 201 to 210 of about 3,588 (251)

Plasma-wall interaction processes in dense thermal plasmas

, 2022
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Plasma Stainless Wall Interaction in the LHD

Plasma Stainless Wall Interaction in the LHD
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Plasma Wall Interactions of ICRF Heated Plasma in LHD

Plasma Wall Interactions of ICRF Heated Plasma in LHD
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Plasma-wall interaction in NET

Journal of Nuclear Materials, 1987
NET is conceived as an experimental reactor with the aim of demonstrating reactor-relevant plasma performance and reliable operation of the device as well as developing and testing components for a demonstration reactor. For power and particle exhaust both a single-null and a double-null poloidal divertor configuration are under consideration.
M F A Harrison, E S Hotston, G Vieider   +2 more
exaly   +2 more sources

Plasma-wall interaction and plasma performance in textor — A review

Journal of Nuclear Materials, 1987
Abstract TEXTOR, a tokamak primarily devoted to plasma-wall interaction studies, has been operated during the last 2–3 years under a wide variety of discharge conditions. Discharges with Ohmic heating only and with additional ICR heating in the MW-range were produced over an extended range of plasma parameters. Different limiter materials were used —
Textor Team, H L Bay, G Bertschinger
exaly   +2 more sources

Development of a Compact Divertor Plasma Simulator for Plasma-Wall Interaction Studies on Neutron-Irradiated Materials [PDF]

Plasma and Fusion Research, 2017
0000-0001-7826-0046We have developed a compact divertor plasma simulator (CDPS) that can produce steady-state deuterium and/or helium plasmas with densities above ∼ 1018 m−3 for Plasma-Wall Interaction (PWI) studies of neutron-irradiated materials.
Nobutada Ohno, Ryo Nishimura, T Toyama   +2 more
exaly   +5 more sources

Plasma-Wall Interactions in ITER

Journal of Nuclear Materials, 1997
Abstract This paper reviews the status of the design of the divertor and first-wall/shield, the main in-vessel components for ITER. Under nominal ignited conditions, 300 MW of alpha power will be produced and must be removed from the divertor and first-wall. Additional power from auxiliary sources up to the level of 100 MW must also be removed in the
Parker, R., De Michelis, C., Janeschitz, G., Ghendrih, P., Pacher, H., Grisolia, C., Post, D., et al., Chiocchio, S., Federici, G., Ladd, P., ITER-Joint-Central-Team, Home-Teams   +12 more
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Issues in the plasma wall interactions in RFX

Journal of Nuclear Materials, 2001
The standard intrinsic nature of transport in reversed field pinches entails that remarkable ohmic power input (20-80 MW) is involved in the all-graphite, MA level RFX device. MHD instabilities restrict the region of plasma-wall interaction (PWI), where power densities >100 may be locally reached.
M Valisa, R Bartiromo, D Bettella, L Carraro, S Costa, P Martin, S Martini, R Pasqualotto, ME Puiatti, P Scarin, F Sattin, G Telesca, P Zanca, B Zaniol, RFX Team   +14 more
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Modeling plasma-wall interactions in First Wall-Limiter geometry

Computer Physics Communications, 2004
We test the standard edge plasma code B2-solps5.0 on a model First-Wall Limiter (FWL) geometry. The presence of a tangency point between the solid wall and the magnetic separatrix introduces a singular point in the geometry. A quadrilateral computational mesh can fit the given configuration only if it is highly distorted, constituting a severe test for
SUBBA, Fabio, ZANINO, Roberto
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Burning Plasma—Wall Interactions

AIP Conference Proceedings, 2009
We have studied chemical sputtering, hydrogen retention and other products of particle‐surface interactions in the least known, intermediate‐to‐low range of impact energies (1–30 eV/D), with atomic and molecular projectiles of deuterated amorphous carbon surfaces.
Predrag S. Krstić, Carlos O. Reinhold, Kevin B. Fournier   +2 more
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