Transport of recycled deuterium to the plasma core in the Tokamak Fusion Test Reactor
- Plasma Physics Laboratory, Princeton University, P.O. Box 451, Princeton, New Jersey08543 (United States)
Fueling of the plasma core by recycling in the Tokamak Fusion Test Reactor [Phys. Plasmas {bold 2}, 2176 (1995)] has been studied. In plasmas fueled by deuterium recycled from the limiter and tritium-only neutral beam injection, the DT neutron rate 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 {ital et al.}, Phys. Plasmas {bold 3}, 4084 (1996)] neutrals code shows that the dependence on radius can be related to the penetration of neutrals through the scrape-off layer. {copyright} {ital 1998 American Institute of Physics.}
- OSTI ID:
- 625846
- Journal Information:
- Physics of Plasmas, Journal Name: Physics of Plasmas Journal Issue: 4 Vol. 5; ISSN PHPAEN; ISSN 1070-664X
- Country of Publication:
- United States
- Language:
- English
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