Title :
The engineering design of TPX
Author_Institution :
Plasma Phys. Lab., Princeton Univ., NJ, USA
Abstract :
The Tokamak Physics Experiment (TPX) is designed to develop the scientific basis for a compact and continuously operating tokamak fusion reactor. TPX has a long pulse (1000s) capability, can accommodate high divertor heat loads, has a flexible PF system, and auxiliary heating and current drive systems that make it an ideal test bed for development of attractive reactor concepts. The design incorporates superconducting magnets in both the toroidal and poloidal field magnets. Long pulse deuterium operation will produce 6×1021 neutrons per year requiring remote maintenance of the in-vessel hardware. This paper provides an overview of the TPX Project and describes the design approach with emphasis on salient features of the tokamak
Keywords :
Tokamak devices; fusion reactor design; fusion reactors; nuclear reactor maintenance; plasma instability; shielding; superconducting magnets; TPX; Tokamak Physics Experiment; auxiliary heating system; current drive system; engineering design; poloidal field magnet; superconducting magnets; toroidal field magnet; Design engineering; Deuterium; Fusion reactor design; Fusion reactors; Heating; Inductors; Physics; Superconducting magnets; System testing; Tokamaks;
Conference_Titel :
Fusion Engineering, 1993., 15th IEEE/NPSS Symposium on
Conference_Location :
Hyannis, MA
Print_ISBN :
0-7803-1412-3
DOI :
10.1109/FUSION.1993.518356
