Published March 2000
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Modeling of neutral beam ion loss from NSTX plasmas
- 1. Princeton Plasma Physics Laboratory, Princeton, NJ (United States)
- 2. UKAEA Culham Laboratory, Abingdon, Oxfordshire (United Kingdom)
- 3. Columbia University, New York, NY (United States)
Description
Beam ion losses from the National Spherical Torus Experiment (NSTX) under a variety of plasma conditions have been modeled using the EIGOL code. This code incorporates the beam deposition and the full gyroorbit of the ions. EIGOL results indicate that 42% of the beam power will be lost to the walls for an equilibrium with β=40%, IP=1 MA, BT=0.3 T, and q0=2.6. The high harmonic fast wave (HHFW) antenna, because it is at the midplane and is closer to the plasma than any other structures, will absorb most of the power from the escaping beam ions. (author)
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Additional details
Publishing Information
- Imprint Title
- Proceedings of the 6th IAEA Technical Committee meeting on energetic particles in magnetic confinement systems
- Imprint Pagination
- 152 p.
- Journal Page Range
- p. 109-112
- Report number
- JAERI-Conf--2000-004
Conference
- Title
- 6. IAEA Technical Committee meeting on energetic particles in magnetic confinement systems
- Dates
- 12-14 Oct 1999
- Place
- Naka, Ibaraki (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 31065693
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BEAM INJECTION HEATING; ENERGY LOSSES; EXPERIMENT PLANNING; ORBITS; PARTICLE LOSSES; SPECIFICATIONS; SPHERICAL CONFIGURATION; TAIL IONS; TOKAMAK DEVICES
- Descriptors DEC
- CHARGED PARTICLES; CLOSED PLASMA DEVICES; CONFIGURATION; HEATING; IONS; LOSSES; PLANNING; PLASMA HEATING; THERMONUCLEAR DEVICES
Optional Information
- Notes
- 4 refs., 3 figs.