Open AccessTransport of Recycled Deuterium to the Plasma Core in TFTR
Author(s) -
M G Bell,
R V Budny,
D L Jassby,
H Park,
C H Skinner
Publication year - 1997
Language(s) - English
Resource type - Reports
DOI - 10.2172/3680
Subject(s) - deuterium , plasma , tokamak fusion test reactor , limiter , tokamak , tritium , atomic physics , pellet , radius , neutron emission , neutron , core (optical fiber) , nuclear physics , chemistry , materials science , physics , neutron temperature , telecommunications , computer security , computer science , composite material
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 the DEGAS neutrals code shows that the dependence on radius can be related to the penetration of neutrals through the scrape-off layer