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Transport of Recycled Deuterium to the Plasma Core in TFTR

Technical Report ·
DOI:https://doi.org/10.2172/3680· OSTI ID:3680
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.
Research Organization:
Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ
Sponsoring Organization:
USDOE Office of Energy Research (ER)
DOE Contract Number:
AC02-76CH03073
OSTI ID:
3680
Report Number(s):
PPPL-3271; ON: DE00003680
Country of Publication:
United States
Language:
English

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