Transport of recycled deuterium to the plasma core in the Tokamak Fusion Test Reactor

摘要

Fueling of the plasma core by recycling in the Tokamak Fusion Test Reactor [Phys. Plasmas 2, 2176 (1995)] has been studied. In plasmas fueled by deuterium recycled from the limiter and tritium-only neutral beam injection, the DT neutron rare provides a measure of the deuterium influx into the core plasma. A reduced influx with plasmas using lithium pellet conditioning: and with plasmas of reduced major (and minor) radius is found. Modeling with the DEGAS [D. P. Stotler et al., Phys. Plasmas 3, 4084 (1996)] neutrals code shows that the dependence on radius can be related to the penetration of neutrals through the scrape-off layer. (C) 1998 American Institute of Physics. [References: 24]