A mock-up of a tritium pellet injector for ITER

The ITER tokamak is to be equipped with a pellet injector for plasma fuelling. A tritium compatible pneumatic pellet injector with a screw extruder has been designed, tested with protium, and is under installation for testing at the experimental tritium loop in the Russian Nuclear Center in Sarov. T...

Ausführliche Beschreibung

Gespeichert in:
Bibliographische Detailangaben
Veröffentlicht in:Fusion engineering and design 2001-11, Vol.58, p.313-317
Hauptverfasser: Viniar, I, Saksaganskii, G, Skoblikov, S, Krasilnikov, I, Pimanikhin, S
Format: Artikel
Sprache:eng
Schlagworte:
Online-Zugang:Volltext
Tags: Tag hinzufügen
Keine Tags, Fügen Sie den ersten Tag hinzu!
Beschreibung
Zusammenfassung:The ITER tokamak is to be equipped with a pellet injector for plasma fuelling. A tritium compatible pneumatic pellet injector with a screw extruder has been designed, tested with protium, and is under installation for testing at the experimental tritium loop in the Russian Nuclear Center in Sarov. The rectangular rod 3×4 mm 2 from condensed protium was extruded within 1500 s at rate of ∼15 mm/s. Pellets ∼3 mm in size formed from the rod were accelerated up to 500 m/s by helium under a pressure of 1 MPa with an injection frequency of 1 and 2 Hz. The main injector subsystems and the current status of the work are described.
ISSN:0920-3796
1873-7196
DOI:10.1016/S0920-3796(01)00360-X