Study of Heating and Fusion Power Production in ITER Discharges

Journal Article · Mon Oct 03 00:00:00 EDT 2011 · AIP Conference Proceedings

DOI:https://doi.org/10.1063/1.3647235· OSTI ID:21611739

Rafiq, T; Kritz, A H; Bateman, G ^[1]; Kessel, C; McCune, D C; Budny, R V ^[2]; Pankin, A Y ^[3]

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1. Department of Physics, Lehigh University, Bethlehem, PA 18015 (United States)
2. PPPL, Princeton University, PO Box 451, Princeton, NJ 08543 (United States)
3. Tech-X Corporation, Boulder, CO 80303 (United States)

ITER simulations, in which the temperatures, toroidal angular frequency and currents are evolved, are carried out using the PTRANSP code starting with initial profiles and boundary conditions obtained from TSC code studies. The dependence of heat deposition and current drive on ICRF frequency, number of poloidal modes, beam orientation, number of Monte Carlo particles and ECRH launch angles is studied in order to examine various possibilities and contingencies for ITER steady state and hybrid discharges. For the hybrid discharges, the fusion power production and fusion Q, computed using the Multi-Mode MMM v7.1 anomalous transport model, are compared with those predicted using the GLF23 model. The simulations of the hybrid scenario indicate that the fusion power production at 1000 sec will be approximately 500 MW corresponding to a fusion Q = 10.0. The discharge scenarios simulated aid in understanding the conditions for optimizing fusion power production and in examining measures of plasma performance.

• OSTI ID: 21611739
• Journal Information: AIP Conference Proceedings, Vol. 1392, Issue 1; Conference: IFP-CNR-Chalmers workshop on nonlinear phenomena in fusion plasmas, Varenna (Italy), 8-10 Jun 2011; Other Information: DOI: 10.1063/1.3647235; (c) 2011 American Institute of Physics; Country of input: International Atomic Energy Agency (IAEA); ISSN 0094-243X
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
BOUNDARY CONDITIONS
CHARGED-PARTICLE TRANSPORT
COMPUTERIZED SIMULATION
ECR HEATING
G CODES
ICR HEATING
ITER TOKAMAK
MONTE CARLO METHOD
OPTIMIZATION
PLASMA
PLASMA SIMULATION
POWER GENERATION
STEADY-STATE CONDITIONS
TRANSPORT THEORY
CALCULATION METHODS
CLOSED PLASMA DEVICES
COMPUTER CODES
HEATING
HIGH-FREQUENCY HEATING
PLASMA HEATING
RADIATION TRANSPORT
SIMULATION
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTORS
TOKAMAK DEVICES
TOKAMAK TYPE REACTORS