Predictive simulations of ITER including neutral beam driven toroidal rotation

Journal Article · Sun Jun 15 00:00:00 EDT 2008 · Physics of Plasmas

DOI:https://doi.org/10.1063/1.2931037· OSTI ID:21120439

Halpern, Federico D; Kritz, Arnold H; Bateman, Glenn; Pankin, Alexei Y ^[1]; Budny, Robert V; McCune, Douglas C ^[2]

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1. Department of Physics, Lehigh University, 16 Memorial Drive East, Bethlehem, Pennsylvania 18015 (United States)
2. Princeton Plasma Physics Laboratory, P. O. Box 451, Princeton, New Jersey 08543 (United States)

Predictive simulations of ITER [R. Aymar et al., Plasma Phys. Control. Fusion 44, 519 (2002)], discharges are carried out for the 15 MA high confinement mode (H-mode) scenario using PTRANSP, the predictive version of the TRANSP code. The thermal and toroidal momentum transport equations are evolved using turbulent and neoclassical transport models. A predictive model is used to compute the temperature and width of the H-mode pedestal. The ITER simulations are carried out for neutral beam injection (NBI) heated plasmas, for ion cyclotron resonant frequency (ICRF) heated plasmas, and for plasmas heated with a mix of NBI and ICRF. It is shown that neutral beam injection drives toroidal rotation that improves the confinement and fusion power production in ITER. The scaling of fusion power with respect to the input power and to the pedestal temperature is studied. It is observed that, in simulations carried out using the momentum transport diffusivity computed using the GLF23 model [R. Waltz et al., Phys. Plasmas 4, 2482 (1997)], the fusion power increases with increasing injected beam power and central rotation frequency. It is found that the ITER target fusion power of 500 MW is produced with 20 MW of NBI power when the pedestal temperature is 3.5 keV.

• OSTI ID: 21120439
• Journal Information: Physics of Plasmas, Vol. 15, Issue 6; Other Information: DOI: 10.1063/1.2931037; (c) 2008 American Institute of Physics; Country of input: International Atomic Energy Agency (IAEA); ISSN 1070-664X
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
CYCLOTRONS
ELECTRON TEMPERATURE
H-MODE PLASMA CONFINEMENT
ICR HEATING
ION CYCLOTRON-RESONANCE
ION TEMPERATURE
IONS
ITER TOKAMAK
NEOCLASSICAL TRANSPORT THEORY
PLASMA
PLASMA BEAM INJECTION
PLASMA SIMULATION
POWER GENERATION
RF SYSTEMS
ROTATION
THERMONUCLEAR REACTIONS
TURBULENCE