Transport of Recycled Deuterium to the Plasma Core in TFTR

Technical Report · Wed Oct 01 00:00:00 EDT 1997

DOI:https://doi.org/10.2172/3680· OSTI ID:3680

Bell, M G; Budny, R V; Jassby, D L; Park, H; Skinner, C H

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 Lab. (PPPL), Princeton, NJ (United States)
• Sponsoring Organization: USDOE Office of Science (SC)
• DOE Contract Number: AC02-76CH03073
• OSTI ID: 3680
• Report Number(s): PPPL-3271; ON: DE00003680
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION
TFTR Tokamak
Limiters
D-T Operation
D Codes
Deuterium
Recycling
Experimental Data
Theoretical Data
Computerized Simulation
Monte Carlo Method