Title :
18th IEEE/NPSS Symposium on Fusion Engineering. Symposium Proceedings (Cat. No.99CH37050)
Abstract :
The following topics were discussed: electrostatic confinement; ARIES-ST; NSTX; materials and diagnostics; vacuum, tritium and safety; divertors and plasma facing components; heating, current drive and maintenance; inertial fusion energy; Fusion Ignition Research Experiment; DIII-D
Keywords :
Tokamak devices; fusion reactor design; fusion reactor diverters; fusion reactor materials; nuclear engineering; plasma diagnostics; plasma heating; plasma inertial confinement; plasma toroidal confinement; ARIES-ST; DIII-D; Fusion Ignition Research Experiment; NSTX; current drive; diagnostics; divertors; electrostatic confinement; heating; inertial fusion energy; maintenance; materials; nuclear fusion; plasma facing components; safety; tritium; vacuum;
Conference_Titel :
Fusion Engineering, 1999. 18th Symposium on
Conference_Location :
Albuquerque, NM, USA
Print_ISBN :
0-7803-5829-5
DOI :
10.1109/FUSION.1999.849780