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Demonstration of Tokamak Discharge Shutdown with Shell Pellet Payload Impurity Dispersal.
Hollmann, E M; Parks, P B; Shiraki, D; Alexander, N; Eidietis, N W; Lasnier, C J; Moyer, R A.
Afiliação
  • Hollmann EM; University of California-San Diego, La Jolla, California 92093, USA.
  • Parks PB; General Atomics, San Diego, California 92186, USA.
  • Shiraki D; Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831, USA.
  • Alexander N; General Atomics, San Diego, California 92186, USA.
  • Eidietis NW; General Atomics, San Diego, California 92186, USA.
  • Lasnier CJ; Lawrence Livermore National Laboratory, Livermore, California 94550, USA.
  • Moyer RA; University of California-San Diego, La Jolla, California 92093, USA.
Phys Rev Lett ; 122(6): 065001, 2019 Feb 15.
Article em En | MEDLINE | ID: mdl-30822084
ABSTRACT
The first rapid tokamak discharge shutdown using dispersive core payload deposition with shell pellets has been achieved in the DIII-D tokamak. Shell pellets are being investigated as a possible new path toward achieving tokamak disruption mitigation with both low conducted wall heat loads and slow current quench. Conventional disruption mitigation injects radiating impurities into the outer edge of the tokamak plasma, which tends to result in poor impurity assimilation and creates a strong edge cooling and outward heat flow, thus requiring undesirable high-Z impurities to achieve low conducted heat loads. The shell pellet technique aims to produce a hollow temperature profile by using a thin, low-ablation shell surrounding a dispersive payload, giving a greatly increased impurity ablation (and radiation) rate when the payload is released in the plasma core. This principle was demonstrated successfully using 3.6 mm outer diameter, 40 µm thickness diamond shells holding boron powder. The pellets caused rapid (<10 ms) discharge shutdown with low conducted divertor heat fluence (∼0.1 MJ/m^{2}). Confirmation of massive release of the boron powder payload into the plasma core was obtained spectroscopically. Some evidence for the formation of a hollow temperature profile during the shutdown was observed. These first results open a new avenue for disruption mitigation research, hopefully enabling development of highly effective methods of avoiding disruption wall damage in future reactor-scale tokamaks.

Texto completo: 1 Coleções: 01-internacional Base de dados: MEDLINE Idioma: En Ano de publicação: 2019 Tipo de documento: Article

Texto completo: 1 Coleções: 01-internacional Base de dados: MEDLINE Idioma: En Ano de publicação: 2019 Tipo de documento: Article