Abstract
Record beta and density values have been obtained at the Small Tight Aspect Ratio Tokamak in the United Kingdom Atomic Energy Agency (UKAEA) Fusion Culham Science Centre by using Oak Ridge National Laboratory's (ORNL's) neutral beam injector for plasma heating. This result has improved the prospects for a future spherical tokamak (ST) fusion core device. To address the physics issues of ST plasmas and the technology of neutral beam heating, ORNL neutral beam injectors have been installed on the Mega Amp Spherical Tokamak (MAST) at UKAEA Culham. The goal of the injectors is to provide a neutral beam heating power of 5 MW for 0.5 s, or up to 4 MW for 5 s. To achieve 5-s operation at the required power level of 4 MW, the existing oxide-filament cathode must be replaced with a cathode having long-pulse capability.In 1983 ORNL developed an advanced positive ion source having long-pulse capability for 50-A and 80-keV hydrogen ion beams. The indirectly heated cathode technology developed for the advanced positive ion source will be utilized to fulfill requirements of long-pulse neutral beam heating on MAST plasmas. The cathode utilizes an electron emitter made of lanthanum oxide (La2O3) doped molybdenum. The cathode is heated by a graphite heater and insulated by a heat shield. The heat shield is made of multiple layers of tantalum sheet. Details of design and performance of such long-pulse cathodes are reported and discussed.
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