Simulation of DIII-D Flat Q Discharges

Simulation of DIII-D Flat Q Discharges PDF Author: C. E. Kessel
Publisher:
ISBN:
Category : Magnetohydrodynamics
Languages : en
Pages : 5

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Simulation of DIII-D Flat Q Discharges

Simulation of DIII-D Flat Q Discharges PDF Author: C. E. Kessel
Publisher:
ISBN:
Category : Magnetohydrodynamics
Languages : en
Pages : 5

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Carnet de route d'un médecin de l'avant...

Carnet de route d'un médecin de l'avant... PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

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Turbulent Transport In Magnetized Plasmas

Turbulent Transport In Magnetized Plasmas PDF Author: C Wendell Horton, Jr
Publisher: World Scientific
ISBN: 9814483885
Category : Science
Languages : en
Pages : 518

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Book Description
The book explains how magnetized plasmas self-organize in states of electromagnetic turbulence that transports particles and energy out of the core plasma faster than anticipated by the fusion scientists designing magnetic confinement systems in the 20th century. It describes theory, experiments and simulations in a unified and up-to-date presentation of the issues of achieving nuclear fusion power.

Analysis and Modeling of DIII-D Hybrid Discharges and Their Extrapolation to ITER.

Analysis and Modeling of DIII-D Hybrid Discharges and Their Extrapolation to ITER. PDF Author: M. R. Wade
Publisher:
ISBN:
Category :
Languages : en
Pages : 6

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Recent experiments on tokamaks around the world [1-5] have demonstrated discharges with moderately high performance in which the q-profile remains stationary, as measured by the motional Stark effect diagnostic, for periods up to several {tau}{sub R}. Hybrid discharges are characterize by q{sub min} {approx} 1, high {beta}{sub N}, and good confinement. These discharges have been termed hybrid because of their intermediate nature between that of an ordinary H-mode and advanced tokamak discharges. They form an attractive scenario for ITER as the normalized fusion performance ({beta}{sub N}H{sub 89P}/q{sub 95}{sup 2}) is at or above that for the ITER baseline Q{sub fus} = 10 scenario, even for q{sub 95} as high as 4.6. The startup phase is thought to be crucial to the ultimate evolution of the hybrid discharge. An open question is how hybrid discharges achieve and maintain their stationary state during the initial startup phase. To investigate this aspect of hybrid discharges, we have used the CORSICA code to model the early stages of a discharge. Results clearly indicate that neoclassical current evolution alone is insufficient to account for the time evolution of the q-profile and that an addition of non-inductive current source must be incorporated into the model to reproduce the experimental time history. We include non-inductive neutral beam and bootstrap current sources in the model, and investigate the difference between simulations with these sources and the experimentally inferred q-profile. Further, we have made preliminary estimates of the spatial structure of the current needed to bring the simulation and experiment into agreement. This additional non-inductive source has not been tied to any physical mechanism as yet. We present these results and discuss the implications for hybrid startup on ITER.

Plasma Physics

Plasma Physics PDF Author: Pablo Martín
Publisher: Springer Science & Business Media
ISBN: 9780792355274
Category : Science
Languages : en
Pages : 1080

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Book Description
This book contains a broad spectrum of plasma physics areas, from magnetic confinement (tokamaks) to spectroscopy in plasmas. The invited papers of the LAWPP present mini-courses for graduate students and review papers in each area, also updating the new ideas in the field.

INTERPRETIVE MODELING OF SIMPLE-AS-POSSIBLE-PLASMA DISCHARGES ON DIII-D USING THE OEDGE CODE.

INTERPRETIVE MODELING OF SIMPLE-AS-POSSIBLE-PLASMA DISCHARGES ON DIII-D USING THE OEDGE CODE. PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 14

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Book Description
Recently a number of major, unanticipated effects have been reported in tokamak edge research raising the question of whether we understand the controlling physics of the edge. This report is on the first part--here focused on the outer divertor--of a systematic study of the simplest possible edge plasma--no ELMs, no detachment, etc.--for a set of 10 repeat, highly-diagnosed, single-null, divertor discharges in DIII-D. For almost the entire, extensive data set so far evaluated, the matches of experiment and model are so close as to imply that the controlling processes at the outer divertor for these simple plasma conditions have probably been correctly identified and quantitatively characterized in the model. The principal anomaly flagged so far relates to measurements of T{sub e} near the target, potentially pointing to a deficiency in our understanding of sheath physics in the tokamak environment.

Nuclear Fusion

Nuclear Fusion PDF Author:
Publisher:
ISBN:
Category : Nuclear fusion
Languages : en
Pages : 332

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The Theory of Toroidally Confined Plasmas

The Theory of Toroidally Confined Plasmas PDF Author: Roscoe B White
Publisher: World Scientific Publishing Company
ISBN: 1911298984
Category : Science
Languages : en
Pages : 389

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Book Description
This invaluable book is designed to provide a basic introduction to plasma equilibrium, particle orbits, transport, and those ideal and resistive magnetohydrodynamic instabilities which dominate the behavior of toroidal magnetically confined plasmas, and to develop the mathematical methods necessary for their theoretical analysis. The book deals primarily with the consequences of ideal and resistive magnetohydrodynamics, these theories being responsible for most of what is well understood regarding the physics of fusion oriented discharges. Contents:Toroidal Configuration: EquilibriumGuiding Center MotionLinear Ideal ModesLinear Resistive ModesNonlinear BehaviorMode-Particle InteractionTransportPhase Integral Methods Readership: Graduate students, researchers and academics in the field of fusion.

Particle Flows in Pumped DIII-D Discharges

Particle Flows in Pumped DIII-D Discharges PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

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Book Description
The dynamics of particle flows in the DIII-D tokamak for two divertor configurations is considered. Fuel and intrinsic carbon impurity flows are analyzed using experimental data and 2D fluid plasma simulations. The flows in puff and pump experiments done in an open and a closed divertor geometry are described. It is shown that the flow of fuel particles is sensitive to divertor geometry. The pumping efficiency of the DIII-D cryopumps is a factor of 2 higher in a closed geometry than an open. The core refueling rate of an open divertor is a factor of 2 higher than that of a closed divertor. In contrast, the flow of impurity carbon particles is insensitive to divertor geometry. Both the core carbon content and the fraction of the carbon source which penetrates to the core is unchanged between an open and closed divertor. In addition, the core impurity content is found to be insensitive to the amplitude of gas puffing in the simulations.

Modeling of Current Profile Evolution and Equilibria in Negative Central Shear Discharges in the DIII-D Experiment

Modeling of Current Profile Evolution and Equilibria in Negative Central Shear Discharges in the DIII-D Experiment PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 7

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Book Description
Recent DIII-D advanced tokamak experiments with negative central shear (NCS) have resulted in operation at high normalized [beta], [beta]{sub N}=[beta]/(I/aB), to 4.2, confinement enhancement factors to H=4 (H=[tau]{sub E}/[tau]ITER-89P), and record neutron rates for DIII-D to 2.4X1016 neutrons/sec. These data were obtained during high triangularity, single and double null diverted operation with peaked (L-mode) and broad (H-mode) pressure profiles. We are modeling the spatial and temporal current profile evolution for these discharges using Corsica, a predictive 1-1/2 D equilibrium and transport code. Current profile evolution is self-consistently determined by including current diffusion resulting from current drive due to early neutral beam injection during the ohmic current ramp-up phase of the discharge and the bootstrap current drive associated with pressure profile evolution.