Transport of recycled deuterium to the plasma core in TFTR [report]

C.H. Skinner, M.G. Bell, R.V. Budny, D.L. Jassby, H. Park, A.T. Ramsey, D.P. Stotler, J.D. Strachan
1997 unpublished
We report a study of the fueling of the plasma core by recycling in the Tokamak Fusion Test Reactor (TFTR) [Phys. Plasmas 2, 2176 (1995)]. We have analyzed discharges fueled by deuterium recycled from the limiter and tritium-only neutral beam injection. In these plasmas, the DT neutron rate provides a measure of the deuterium influx into the core plasma. We find a reduced influx with plasmas using lithium pellet conditioning and with plasmas of reduced major (and minor) radius. Modeling with
more » ... s. Modeling with the DEGAS neutrals code shows that the dependence on radius can be related to the penetration of neutrals through the scrape-off layer.
doi:10.2172/304220 fatcat:sebkx63wh5gclh42noszwc7hiq