DocumentCode
2079118
Title
The ORNL plasma fueling program
Author
Gouge, M.J. ; Milora, S.L. ; Foster, C.A. ; Combs, S.K. ; Fisher, P.W. ; Tsai, C.C. ; Argo, B.E. ; Barber, G.C. ; Baylor, L.R. ; Fehling, D.T. ; Foust, C.R. ; Jernigan, T.C. ; Qualls, A.L. ; Schechter, D.E. ; Simmons, D.W. ; Sohns, C.W. ; Sparks, D.O.
Author_Institution
Oak Ridge Nat. Lab., TN, USA
fYear
1989
fDate
2-6 Oct 1989
Firstpage
1299
Abstract
Advanced plasma fueling systems for magnetic confinement devices are under development at the Oak Ridge National Laboratory (ORNL). The general approach is to produce and accelerate frozen hydrogen-isotope pellets at speeds ranging from 1 to 2 km/s and higher. Recently, ORNL provided pneumatic-based pellet fueling systems for two of the world´s largest tokamak experiments, the Tokamak Fusion Test Reactor (TFTR) and the Joint European Torus (JET). A new, versatile, centrifuge-type injector is being installed on the Tore Supra tokamak. Also, a new, simplified, eight-shot injector has been developed, and injectors based on this design are operating on the Princeton Beta Experiment (PBX) and the ORNL Advanced Toroidal Facility (ATF). In addition to these confinement-physics-related activities, ORNL is pursuing advanced technologies to achieve pellet velocities significantly in excess of 2 km/s, and has carried out a tritium proof of principle experiment in which the fabrication and acceleration of tritium pellets were demonstrated. These ongoing activities are described
Keywords
fusion reactor fuel; materials preparation; tritium; 1000 to 1200 m/s; ATF; Advanced Toroidal Facility; JET; Joint European Torus; ORNL; PBX; Princeton Beta Experiment; T pellet; TFTR; Tokamak Fusion Test Reactor; Tore Supra tokamak; centrifuge-type injector; eight-shot injector; fabrication; frozen H isotope pellets; magnetic confinement devices; plasma fueling program; pneumatic-based pellet fueling systems; Acceleration; Fusion reactor design; Inductors; Laboratories; Magnetic confinement; Plasma accelerators; Plasma confinement; Plasma devices; System testing; Tokamaks;
fLanguage
English
Publisher
ieee
Conference_Titel
Fusion Engineering, 1989. Proceedings., IEEE Thirteenth Symposium on
Conference_Location
Knoxville, TN
Type
conf
DOI
10.1109/FUSION.1989.102450
Filename
102450
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