Full Wave Simulations of Fast Wave Efficiency and Power Losses in the Scrape-off Layer of Tokamak Plasmas in Mid/high Harmonic and Minority Heating Regimes

Full Wave Simulations of Fast Wave Efficiency and Power Losses in the Scrape-off Layer of Tokamak Plasmas in Mid/high Harmonic and Minority Heating Regimes PDF Author:
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Category :
Languages : en
Pages :

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Several experiments on different machines and in different fast wave (FW) heating regimes, such as hydrogen minority heating and high harmonic fast waves (HHFW), have found strong interaction between radio-frequency (RF) waves and the scrape-off layer (SOL) region. This paper examines the propagation and the power loss in the SOL by using the full wave code AORSA, in which the edge plasma beyond the last closed flux surface (LCFS) is included in the solution domain and a collisional damping parameter is used as a proxy to represent the real, and most likely nonlinear, damping processes. 2D and 3D AORSA results for the National Spherical Torus eXperiment (NSTX) have shown a strong transition to higher SOL power losses (driven by the RF field) when the FW cut-off is removed from in front of the antenna by increasing the edge density. Here, full wave simulations have been extended for 'conventional' tokamaks with higher aspect ratios, such as the DIII-D, Alcator C-Mod, and EAST devices. DIII-D results in HHFW regime show similar behavior found in NSTX and NSTX-U, consistent with previous DIII-D experimental observations. In contrast, a different behavior has been found for C-Mod and EAST, which operate in the minority heating regime.

Full Wave Simulations of Fast Wave Mode Conversion and Lower Hybrid Wave Propagation in Tokamaks

Full Wave Simulations of Fast Wave Mode Conversion and Lower Hybrid Wave Propagation in Tokamaks PDF Author: John C. Wright
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Category :
Languages : en
Pages : 16

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Fast Wave (FW) studies of mode conversion (MC) processes at the ion -- ion hybrid layer in toroidal plasmas N must capture the disparate scales of the FW and mode converted ion Bernstein (IBW) and ion cyclotron waves (ICW). Correct modeling of the MC layer requires resolving wavelengths on the order of k pi~1 which leads to a scaling of the maximum poloidal mode number, Mmax, proportional to 1/p (p=pi/L). The computational resources needed a scale with the number of radial (Nr), poloidal (No), and toroidal (No) elements as Nr * No * N3o. Two full wave codes, a massively-parallel-processor (MPP) version of the TORIC-2D finite Larmor radius code [M. Brambilla, Plasma Phys. Controlled Fusion 41, 1 (1999)] and also an all orders spectral code AORSA2D [E. F. Jaeger et al., Phys. Plasmas 9, 1873 (2002) ], have been developed which for the first time are capable of achieving the resolution and speed necessary to address mode conversion phenomena in full two-dimensional (2-D) toroidal geometry. These codes have been used in conjunction with theory and experimental data from the Alcator C-Mod [I. H. Hutchinson et al., Phys. Plasmas 1, 1511 (1994)] to gain new understanding into the nature of FWMC in tokamaks. The MPP version of TORIC is also now capable of running with sufficient resolution to model planned lower hybrid range of frequencies (LHRF) experiments in the Alcator C-Mod.

Fast Wave Injection Into High Temperature Tokamak Plasmas in the Lower-hybrid-density Regime If JIPP T-IIU

Fast Wave Injection Into High Temperature Tokamak Plasmas in the Lower-hybrid-density Regime If JIPP T-IIU PDF Author:
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Category : Electron distribution
Languages : en
Pages : 36

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Fast-Wave Heating of a Reactor Plasma

Fast-Wave Heating of a Reactor Plasma PDF Author: Thomas Howard Stix
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Category : Plasma (Ionized gases)
Languages : en
Pages : 10

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Fast Wave Propagation and Minority Ion Heating Current Drive in a Two-ion Species Tokamak Plasma

Fast Wave Propagation and Minority Ion Heating Current Drive in a Two-ion Species Tokamak Plasma PDF Author: Kin-lu Wong
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ISBN:
Category : Deuterium
Languages : en
Pages : 146

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Fast Wave Heating and Current Drive in Tokamak Plasmas with Negative Central Shear

Fast Wave Heating and Current Drive in Tokamak Plasmas with Negative Central Shear PDF Author:
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Category :
Languages : en
Pages : 8

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Fast waves provide an excellent tool for heating electrons and driving current in the central region of tokamak plasmas. In this paper, we report the use of centrally peaked electron heating and current drive to study transport in plasmas with negative central shear (NCS). Tokamak plasmas with NCS offer the potential of reduced energy transport and improved MHD stability properties, but will require non-inductive current drive to maintain the required current profiles. Fast waves, combined with neutral beam injection, provide the capability to change the central current density evolution and independently vary {ital T{sub e}}, and {ital T{sub i}} for transport studies in these plasmas. Electron heating also reduces the collisional heat exchange between electrons and ions and reduces the power deposition from neutral beams into electrons, thus improving the certainty in the estimate of the electron heating. The first part of this paper analyzes electron and ion heat transport in the L-mode phase of NCS plasmas as the current profile resistively evolves. The second part of the paper discusses the changes that occur in electron as well as ion energy transport in this phase of improved core confinement associated with NCS.

Full-wave Calculation of Fast-wave Current Drive in Tokamaks Including K Sub Parallel Upshifts

Full-wave Calculation of Fast-wave Current Drive in Tokamaks Including K Sub Parallel Upshifts PDF Author:
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Category :
Languages : en
Pages : 6

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Application of Very High Harmonic Fast Waves for Off-axis Current Drive in the DIII-D and FNSF-AT Tokamaks

Application of Very High Harmonic Fast Waves for Off-axis Current Drive in the DIII-D and FNSF-AT Tokamaks PDF Author:
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Category :
Languages : en
Pages :

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Fast waves at frequencies far above the ion cyclotron frequency and approaching the lower hybrid frequency (also called "helicons" or "whistlers") have application to off-axis current drive in tokamaks with high electron beta. The high frequency causes the whistler-like behavior of the wave power nearly following field lines, but with a small radial component, so the waves spiral slowly toward the plasma center. The high frequency also contributes to strong damping. Modeling predicts robust off-axis current drive with good efficiency compared to alternatives in high performance discharges in DIII-D and Fusion Nuclear Science Facility (FNSF) when the electron beta is above about 1.8%. Detailed analysis of ray behavior shows that ray trajectories and damping are deterministic (that is, not strongly affected by plasma profiles or initial ray conditions), unlike the chaotic ray behavior in lower frequency fast wave experiments. Current drive was found to not be sensitive to the launched value of the parallel index of refraction n.

Fast Wave Injection Into High Temperature Tokamak Plasmas in the Lower-hybrid-density Regime of JIPP T-IIU

Fast Wave Injection Into High Temperature Tokamak Plasmas in the Lower-hybrid-density Regime of JIPP T-IIU PDF Author: K. Toi
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Category :
Languages : en
Pages : 30

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Simulation of the Scrape-off Layer Plasma During a Disruption

Simulation of the Scrape-off Layer Plasma During a Disruption PDF Author:
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Category :
Languages : en
Pages : 16

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The evolution of the scrape-off layer (SOL) during a disruption in the DIII-D tokamak is modeled using the 2-D UEDGE transport code. The focus is on the thermal quench phase when most of the energy content of the discharge is rapidly transported across the magnetic separatrix where it then flows to material surfaces or is radiated. Comparisons between the simulation and an experiment on the DIII-D tokamak are made with the heat flux to the divertor plate, and temperature and density profiles at the SOL midplane. The temporal response of the separate electron and ion heat-flux components to the divertor plate is calculated. The sensitivity of the solution to assumptions of electron heat-flux models and impurity radiation is investigated.