Core Plasma Characteristics of a Spherical Tokamak D-3He Fusion Reactor

2005 ◽  
Vol 7 (2) ◽  
pp. 2767-2772 ◽  
Author(s):  
Shi Bingren
Keyword(s):  
Fusion Reactor ◽  
Spherical Tokamak ◽  
Core Plasma ◽  
Plasma Characteristics

scholarly journals H-Mode Power Threshold Studies on MAST

Plasma ◽  
2019 ◽  
Vol 2 (3) ◽  
pp. 328-338 ◽  
Author(s):  
Yasmin Andrew ◽  
Jan-Peter Bähner ◽  
Ronan Battle ◽  
Tomas Jirman
Keyword(s):  
Wave Model ◽  
Plasma Electron ◽  
Spherical Tokamak ◽  
Plasma Current ◽  
Reasonable Condition ◽  
Core Plasma ◽  
Height Dependence ◽  
Power Threshold ◽  
Point Distance ◽  
Plasma Electron Density

Analysis of the L–H and H–L transition power thresholds (Pth) and pedestal parameters are presented for the mega ampere spherical tokamak (MAST). The dependencies of Pth on the average, core plasma electron density, X-point height, and plasma current are described. Increasing X-point distance from the divertor floor over 10–12 cm is found to increase Pth by a factor of three, while X-point heights greater than this have no further influence. The X-point height dependence of Pth is also observed to be sensitive to the plasma current. An Ip decrease from 0.77 MA to 0.65 MA, is observed to lower Pth by a factor of three across the X-point height scan and increases the maximum X-point height at which Pth stops increasing by 3 cm. Finally, a comparison of the experimental results with the predictions by the finite beta drift wave model is made, which provides a reasonable condition for the transition into and out of the H-mode.

Edge plasma characteristics in the helicity injected torus (HIT-II) spherical tokamak

2003 ◽  
Vol 45 (7) ◽  
pp. 1283-1295 ◽  
Author(s):  
K K Jain ◽  
A J Redd ◽  
T R Jarboe ◽  
B A Nelson ◽  
the HIT Team
Keyword(s):  
Edge Plasma ◽  
Spherical Tokamak ◽  
Plasma Characteristics

scholarly journals Effect of the Pitch Modulation of Helical Coils on the Core Plasma Performance of the LHD-Type Helical Fusion Reactor

2021 ◽  
Vol 16 (0) ◽  
pp. 1405085-1405085
Author(s):  
Takuya GOTO ◽  
Katsuji ICHIGUCHI ◽  
Hitoshi TAMURA ◽  
Junichi MIYAZAWA ◽  
Shinsuke SATAKE ◽  
...  
Keyword(s):  
Fusion Reactor ◽  
The Core ◽  
Core Plasma ◽  
Helical Coils

Alignment of small He-Bubbles during in situ deformation of Al-foils

1978 ◽  
Vol 36 (1) ◽  
pp. 396-397
Author(s):  
E. Ruedl ◽  
P. Schiller
Keyword(s):  
Fusion Reactor ◽  
Matrix Material ◽  
Fusion Reactors ◽  
First Wall ◽  
Potential Matrix ◽  
In Situ Deformation ◽  
Α Particles ◽  
Metal Aluminium

The low Z metal aluminium is a potential matrix material for the first wall in fusion reactors. A drawback in the application of A1 is the rel= atively high amount of He produced in it under fusion reactor conditions. Knowledge about the behaviour of He during irradiation and deformation in Al, especially near the surface, is therefore important.Using the TEM we have studied Al disks of 3 mm diameter and 0.2 mm thickness, which were perforated at the centre by double jet polishing. These disks were bombarded at∽200°C to various doses with α-particles, impinging at any angle and energy up to 1.5 MeV at both surfaces. The details of the irradiations are described in Ref.1. Subsequent observation indicated that in such specimens uniformly distributed He-bubbles are formed near the surface in a layer several μm thick (Fig.1).After bombardment the disks were deformed at 20°C during observation by means of a tensile device in a Philips EM 300 microscope.

Fusion reactor aims to rival ITER

Nature ◽  
2010 ◽  
Author(s):  
Emiliano Feresin
Keyword(s):  
Fusion Reactor
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