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Author Budny, R. V. ♦ McCune, D. C. ♦ Redi, M. H. ♦ Schivell, J. ♦ Wieland, R. M.
Source United States Department of Energy Office of Scientific and Technical Information
Content type Text
Language English
Subject Keyword PLASMA PHYSICS AND FUSION ♦ ITER TOKAMAK ♦ PLASMA SIMULATION ♦ THERMONUCLEAR DEVICES ♦ BEAM INJECTION ♦ HELIUM ♦ SAWTOOTH OSCILLATIONS ♦ FUSION YIELD ♦ PLASMA HEATING ♦ ALPHA PARTICLES ♦ COMPUTER CODES ♦ COMPUTERIZED SIMULATION
Abstract The TRANSP code is used to construct comprehensive, self-consistent models for plasmas within the separatrix surface in the International Thermonuclear Experimental Reactor (ITER) [{ital Technical} {ital Basis} {ital for} {ital the} {ital ITER} {ital Interim} {ital Design} {ital Report}, {ital Cost} {ital Review} {ital and} {ital Safety} {ital Analysis} (International Atomic Energy Agency, Vienna, 1996)]. Steady state profiles of two plasmas from the ITER {open_quote}{open_quote}Interim Design{close_quote}{close_quote} database are used. Effects of 1 MeV neutral beam injection, sawteeth mixing, toroidal field ripple, and helium ash transport are included. Results are given for the fusion rate profiles, and parameters describing effects such as the alpha particle heating of electrons and thermal ions, and the thermalization rates. The modeling indicates that the deposition of the neutral beam ions will peak in the plasma center, and the average beam ion energy will be half the injected energy. Sawtooth mixing will broaden the fast alpha profile. The toroidal ripple loss rate of alpha energy will be 3{percent} before sawtooth crashes and will increase by a factor of 3 immediately following sawtooth crashes. Various assumptions for the thermal He transport and the He recycling coefficient at the separatrix {ital R}{sub rec} are used. If the ratio of helium and energy confinement times, {tau}{sup *}{sub He}/{tau}{sub {ital E}} is less than 15, the steady state fusion power is predicted to be 1.5 GW or greater. The values of the transport coefficients required for this fusion power depend on {ital R}{sub rec}. If this is larger than about 0.5, and if the inward pinch is small the required He diffusivity must be much larger than that measured in tokamaks. {copyright} {ital 1996 American Institute of Physics.}
ISSN 1070664X
Educational Use Research
Learning Resource Type Article
Publisher Date 1996-12-01
Publisher Department Princeton Plasma Physics Laboratory
Publisher Place United States
Journal Physics of Plasmas
Volume Number 3
Issue Number 12
Organization Princeton Plasma Physics Laboratory


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