Published May 1984 | Version v1
Journal article

An advanced pump limiter experiment of large toroidal extent - ALT II

  • 1. California Univ., Los Angeles (USA). School of Engineering and Applied Science
  • 2. Princeton Univ., NJ (USA). Plasma Physics Lab.
  • 3. Sandia National Labs., Albuquerque, NM (USA)

Description

Concepts for an advanced pump limiter experiment able to exhaust 5-10% of the plasma particle flux and remove 200 W/cm2 of heat flux on the limiter face are developed and analyzed. An axisymmetric toroidal belt limiter has a compound curvature blade with edges that extend one particle e-folding distance into the scrape-off layer plasma. Approximately 30% of the plasma efflux flows in a gap between the bottom of the limiter blade and the top of either a structural floor, a plenum box or a liner. Neutralizer/deflector plates are located in discrete pairs at each pumping duct and are designed to optimally scatter neutralized particles into the pump ducts. An alternative design consists of a central toroidal spine beneath the blade which scatters plasma as neutral gas into a plenum box. For application to the TEXTOR tokamak with 1.5 MW of ICRF heating and 2,6 MW of 50 keV neutral beam injection, detailed analysis shows that an average heat flux is approximately 200 W/cm2 and that the localized collector plate design is about five times more efficient than the spinal design for particle removal. (orig.)

Additional details

Publishing Information

Journal Title
J. Nucl. Mater.
Journal Volume
121
Series
CODEN: JNUMA.;J. Nucl. Mater.
Journal Page Range
350-360
ISSN
0022-3115

Conference

Title
Symposium on energy removal and particle control in toroidal devices.
Dates
26-29 Jul 1983.
Place
Princeton, NJ (USA).