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  • 1970-1974  (2)
  • 1910-1914
  • 1974  (2)
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  • 1970-1974  (2)
  • 1910-1914
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  • 1
    Electronic Resource
    Electronic Resource
    Axial contraction in toroidal pinches with non-circular plasma cross-sections (1974)
    Springer
    The European physical journal 269 (1974), S. 35-39 
    Details
    ISSN: 1434-601X
    Source: Springer Online Journal Archives 1860-2000
    Topics: Physics
    Notes: Abstract The axial contraction of linear pinches with racetrack-shaped and elliptic cross sections is studied byδW-analysis near the equilibrium shape. A surface current profile and a fixed plasma cross-section area are assumed. It is shown for the corresponding special perturbation thatδW is given by the variation of the surface energy(δW=δW s =1/8B p 2 ξ b 2 ), and thatδW is nearly independent of the shape of the plasma (racetrack or ellipse). The axial oscillation frequency is found to beΩ ax=1/2√CB p /√ρl with a constantC〈1. The model correctly predicts theB p and ρl-dependences of the experimental belt-pinch results and yields theoreticalΩ ax-values a factor of 2 above the experimental ones.
    Type of Medium: Electronic Resource
    URL: http://dx.doi.org/10.1007/BF01668866
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    Paper (German National Licenses)
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  • 2
    Electronic Resource
    Electronic Resource
    Neutron flux distribution on the wall of toroidal controlled thermonuclear reactor devices with elongated cross section (1974)
    Springer
    The European physical journal 269 (1974), S. 41-46 
    Details
    ISSN: 1434-601X
    Source: Springer Online Journal Archives 1860-2000
    Topics: Physics
    Notes: Abstract The neutron flux distribution on the wall of a toroidal CTR device with strongly elongated cross section is calculated. On the inner and outer cylindrical walls (belt-pinch device) the flux distribution has a plateau region with a half-width equal to about the height of the plasma. The maximum flux is found on the outer cylinder and in the symmetry plane (z 0=0). The neutron flux asymmetry and reductionη of the mean wall loading are determined. For standard data anη of 57% is computed. This is mainly due to the flux profiles on the cylindrical walls and does not depend sensitively on the toroidal curvature. For standard parameters the inner cylinder absorbs 22.6%, the outer cylinder 68.6% and the end plates together 8.8% of the total neutron emission. The corresponding values for a straight device with the same coil and plasma cross section are 44%, 44% and 12%. A reduction of toroidal curvature diminishes flux asymmetry between the inner and outer cylinders. The maximum flux and minimumη-value are obtained at a large torus radius equal to two times the coil width. For small aspect ratios (R t W0.5) the neutron flux through the inner cylinder becomes so small that its interior may be filled with a material other than a blanket material, e.g. with an iron core.
    Type of Medium: Electronic Resource
    URL: http://dx.doi.org/10.1007/BF01668867
    Library Location Call Number Volume/Issue/Year Availability
    BibTip Others were also interested in ...
    Paper (German National Licenses)
    Fulltext
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