Multi-Mode transport modeling of the International Thermonuclear Experimental Reactor (ITER)

Journal Article · Mon Jun 01 04:00:00 EDT 1998 · Physics of Plasmas

DOI:https://doi.org/10.1063/1.872909· OSTI ID:616862

Bateman, G; Kritz, A H; Kinsey, J E; Redd, A J ^[1]

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1. Physics Department, Lehigh University, 16 Memorial Drive East, Bethlehem, Pennsylvania18015 (United States)

Predictions are made for the performance of the International Thermonuclear Experimental Reactor (ITER) [R. Aymar, V. Chuyanov, M. Huguet, R. Parker, and Y. Shimomura, in {ital Proceedings of the Sixteenth International Atomic Energy Agency Fusion Energy Conference, Montr{acute e}al, Canada 1996} (International Atomic Energy Agency, Vienna, 1997), Paper IAEA-CN-64/01-1] design using the Multi-Mode model in the time-dependent one- and one-half-dimensional (1-1/2-D) BALDUR [C. E. Singer {ital et al.}, Comput. Phys. Commun. {bold 49}, 275 (1988)] transport code. This model predicts the temperature and density profiles observed in present-day tokamak experiments more closely on the average than other models currently available. Simulations using the Multi-Mode transport model, with its inherent gyro-Bohm scaling, indicate that ITER will ignite, even with edge temperatures as low as 0.25 keV (L-mode, or low-confinement mode, boundary conditions) or with volume averaged density as low as 0.775{times}10{sup 20}m{sup {minus}3} (just below the Greenwald density limit, when T{sub edge}=0.75keV). The ignition is found to be thermally stable, and the fusion power production is easily controlled by varying plasma density, impurity content, or edge temperatures. The nonequilibrium impurity radiation model used in these simulations predicts that a significant fraction of the fusion power is radiated when conditions are close to marginal ignition. {copyright} {ital 1998 American Institute of Physics.}

• OSTI ID: 616862
• Journal Information: Physics of Plasmas, Journal Name: Physics of Plasmas Journal Issue: 6 Vol. 5; ISSN PHPAEN; ISSN 1070-664X
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
CHARGED-PARTICLE TRANSPORT
DESIGN
ITER TOKAMAK
PERFORMANCE
PLASMA DENSITY
PLASMA IMPURITIES
PLASMA SIMULATION
POWER