Results 261 to 270 of about 40,420 (297)
Effects of Wall Conditionings on LHD Plasma Facing Walls
Effects of Wall Conditionings on LHD Plasma Facing Wallsopenaire
Wall conditioning of JET with the ITER-Like Wall
Journal of Nuclear Materials, 2013 The initial conditioning cycle of \{JET\} ILW\} is analysed and compared with restart and operation in 2008 with a carbon dominated wall. Comparable water and oxygen decay times are observed during bake-out in both cases. Despite a 2 × 10−3 mbar l/s leak rate during plasma operation, no further wall conditioning has been necessary after plasma restart ...
Douai, D. +13 more
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Vacuum, 1996
Abstract This article presents plans for wall conditioning for ITER. Typical machine parameters are 1.5 GW of fusion power and 1000 s of DT burn duration. To achieve these plasma, the wall conditioning is required in ITER. For baseline methods, glow discharge cleaning for zero-magnetic field, and electron cyclotron resonance discharge cleaning and ...
H Nakamura, J Dietz, P Ladd
exaly +2 more sources
Abstract This article presents plans for wall conditioning for ITER. Typical machine parameters are 1.5 GW of fusion power and 1000 s of DT burn duration. To achieve these plasma, the wall conditioning is required in ITER. For baseline methods, glow discharge cleaning for zero-magnetic field, and electron cyclotron resonance discharge cleaning and ...
H Nakamura, J Dietz, P Ladd
exaly +2 more sources
The wall conditioning techniques in RFX
Vacuum, 1996 The vacuum vessel of RFX has a total volume of 10 m(3) and a surface exposed to the vacuum of 40 m(2). It is completely covered with 2016 graphite tiles. The following wall conditioning techniques are applied: baking up to 350 degrees C, GDC and PDC in H-2 and He. Moreover, in order to reduce Z(eff) in the plasma discharge, a GDC assisted deposition of
P. Sonato +11 more
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Wall boundary conditions for rough walls
Progress in Computational Fluid Dynamics, An International Journal, 2007The treatment of rough walls is still a considerable challenge in computational fluid dynamics. Empirical wall functions are available to bridge the flow and shear stress in the near-wall computational cells to the wall distance and roughness. The concept of equivalent sand-grain roughness has been applied.
Alireza Ashrafian, Stein Tore Johansen
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Journal of Nuclear Materials, 1974
Abstract ORMAK is a diffuse toroidal pinch with typical plasma currents of 100 kA, electron temperatures of 800 eV, and ion temperatures of 300 eV. The walls of the plasma region are made of stainless steel coated with an intermediate layer of platinum 0.5 μm thick and an outer 1–2 μm layer of gold.
Colchin, R. J. +9 more
openaire +1 more source
Abstract ORMAK is a diffuse toroidal pinch with typical plasma currents of 100 kA, electron temperatures of 800 eV, and ion temperatures of 300 eV. The walls of the plasma region are made of stainless steel coated with an intermediate layer of platinum 0.5 μm thick and an outer 1–2 μm layer of gold.
Colchin, R. J. +9 more
openaire +1 more source
Journal of Nuclear Materials, 2011
Abstract Like all tokamaks, ITER will require wall conditioning systems and strategies for successful operation from the point of view of plasma-facing surface preparation. Unlike today’s devices however, ITER will have to manage large quantities of tritium fuel, imposing on wall conditioning a major responsibility for tritium inventory control.
Michiya Shimada, Richard A. Pitts
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Abstract Like all tokamaks, ITER will require wall conditioning systems and strategies for successful operation from the point of view of plasma-facing surface preparation. Unlike today’s devices however, ITER will have to manage large quantities of tritium fuel, imposing on wall conditioning a major responsibility for tritium inventory control.
Michiya Shimada, Richard A. Pitts
openaire +1 more source
Fusion Science and Technology, 2010
Wall conditioning in the Large Helical Device (LHD) has been conducted successively since the first experimental campaign in 1998.
S. Masuzaki +12 more
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Wall conditioning in the Large Helical Device (LHD) has been conducted successively since the first experimental campaign in 1998.
S. Masuzaki +12 more
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Journal of Nuclear Materials, 1984
Abstract We summarize the experience gained over two years on the wall conditioning of TEXTOR by radiofrequency assisted DC glow discharges (RG-discharges). The importance of the contamination history of the wall for the cleaning rate in H2 RG-discharges is underlined. RG-discharges in hydrogen already lead to some sputter erosion of the wall.
J. Winter +7 more
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Abstract We summarize the experience gained over two years on the wall conditioning of TEXTOR by radiofrequency assisted DC glow discharges (RG-discharges). The importance of the contamination history of the wall for the cleaning rate in H2 RG-discharges is underlined. RG-discharges in hydrogen already lead to some sputter erosion of the wall.
J. Winter +7 more
openaire +1 more source