Author: A. Thyagaraja
Publisher:
ISBN:
Category : Fusion reactors
Languages : en
Pages : 14
Book Description
Global Numerical Simulations of Turbulence and Transport in a Tokamak
Author: A. Thyagaraja
Publisher:
ISBN:
Category : Fusion reactors
Languages : en
Pages : 14
Book Description
Publisher:
ISBN:
Category : Fusion reactors
Languages : en
Pages : 14
Book Description
Numerical Simulations of Tokamak Plasma Turbulence and Internal Transport Barriers
Author: A. Thyagaraja
Publisher:
ISBN:
Category : Plasma turbulence
Languages : en
Pages : 18
Book Description
Publisher:
ISBN:
Category : Plasma turbulence
Languages : en
Pages : 18
Book Description
Direct Numerical Simulations of Long-wavelength Tokamak Turbulence and Transport Using CUTIE - Electrostatic Nonadiabaticity Model
Author: A. Thyagaraja
Publisher:
ISBN:
Category : Magnetohydrodynamics
Languages : en
Pages : 27
Book Description
Publisher:
ISBN:
Category : Magnetohydrodynamics
Languages : en
Pages : 27
Book Description
Direct Numerical Simulations of Long-wavelength Tokamak Turbulence and Transport Using CUTIE-electrostatic Nonadiabatcity Model
Author: A. Thyagaraja
Publisher:
ISBN:
Category : Plasma turbulence
Languages : en
Pages : 27
Book Description
Publisher:
ISBN:
Category : Plasma turbulence
Languages : en
Pages : 27
Book Description
Numerical Simulation of Tokamak Plasma Turbulence and Internal Transport Barriers
Author: A. Thyagaraja
Publisher:
ISBN:
Category : Agricultural engineering
Languages : en
Pages :
Book Description
Publisher:
ISBN:
Category : Agricultural engineering
Languages : en
Pages :
Book Description
Global 3D Two-fluid Simulations of Turbulent Transport at Tokamak Edge Region
Author: Ben Zhu
Publisher:
ISBN:
Category :
Languages : en
Pages : 206
Book Description
A new global 3D two-fluid code, GDB, based on the drift-reduced Braginskii model has been developed and tested to study the turbulent transport across the entire tokamak edge region: from plasma sources in the inner core to plasma sinks in the outer-most scrape-off layer (SOL). In this code, profiles of plasma density, electron and ion temperature, electric potential, magnetic flux and parallel flow are evolved self-consistently. Milliseconds-long simulations are carried out in a shifted-circle magnetic configuration with realistic Alcator C-Mod tokamak inner wall limited (IWL) discharge parameters. The resistive ballooning instability is identified as the predominant driver of edge turbulence in the L-mode regime. Simulations show, in agreement with experimental observations, as the simulation moves towards density limit regime by increasing density, the turbulent transport is drastically enhanced and the plasma profiles are relaxed; on the other hand, as the simulation approaches to the H-mode regime by increasing temperature, the turbulent transport is suppressed and plasma profiles are steepened with a pedestal-like structure forming just inside of the separatrix. Radial transport level and turbulence statistics of these simulations also qualitatively match the experimental measurements. Spontaneous E x B rotation in the electron diamagnetic drift direction in the closed flux region are observed in all cases. It can be explained based on the steady state ion continuity relation [mathematical equation]. E x B rotation in the closed flux region is found mostly cancels the ion diamagnetic drift as H-mode-like regimes are approached, and exceeds it by a factor of two or more at lower temperatures due to parallel ion flows.
Publisher:
ISBN:
Category :
Languages : en
Pages : 206
Book Description
A new global 3D two-fluid code, GDB, based on the drift-reduced Braginskii model has been developed and tested to study the turbulent transport across the entire tokamak edge region: from plasma sources in the inner core to plasma sinks in the outer-most scrape-off layer (SOL). In this code, profiles of plasma density, electron and ion temperature, electric potential, magnetic flux and parallel flow are evolved self-consistently. Milliseconds-long simulations are carried out in a shifted-circle magnetic configuration with realistic Alcator C-Mod tokamak inner wall limited (IWL) discharge parameters. The resistive ballooning instability is identified as the predominant driver of edge turbulence in the L-mode regime. Simulations show, in agreement with experimental observations, as the simulation moves towards density limit regime by increasing density, the turbulent transport is drastically enhanced and the plasma profiles are relaxed; on the other hand, as the simulation approaches to the H-mode regime by increasing temperature, the turbulent transport is suppressed and plasma profiles are steepened with a pedestal-like structure forming just inside of the separatrix. Radial transport level and turbulence statistics of these simulations also qualitatively match the experimental measurements. Spontaneous E x B rotation in the electron diamagnetic drift direction in the closed flux region are observed in all cases. It can be explained based on the steady state ion continuity relation [mathematical equation]. E x B rotation in the closed flux region is found mostly cancels the ion diamagnetic drift as H-mode-like regimes are approached, and exceeds it by a factor of two or more at lower temperatures due to parallel ion flows.
Global Confinement Properties in Global, Flux-driven, Gyrokinetic Simulations
Author: Elisabetta Caschera
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Understanding and predicting the performance of a fusion reactor in terms of confinement is one of the missing milestones for the availability of fusion energy. The predictions for the design of future reactors such as ITER are based on the extrapolation of empiricalscaling laws. We investigate global confinement properties of turbulent heat transport in a Tokamak with first principle simulations. The research is carried on two main topics: the scaling properties of plasma confinement and the effect of the plasma boundary on the turbulent transport. An important result is obtained when reproducing the global scaling for the energy confinement time with numerical simulations. However the scaling properties are found to brake at the local level. The boundary condition of the code has been modified to mimic the experimental Scrape-Off Layer at the plasma edge. Additional physics is now accessible, such as Kelvin-Helmholtz-like instability at separatrix and edge subcritical turbulence.
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Understanding and predicting the performance of a fusion reactor in terms of confinement is one of the missing milestones for the availability of fusion energy. The predictions for the design of future reactors such as ITER are based on the extrapolation of empiricalscaling laws. We investigate global confinement properties of turbulent heat transport in a Tokamak with first principle simulations. The research is carried on two main topics: the scaling properties of plasma confinement and the effect of the plasma boundary on the turbulent transport. An important result is obtained when reproducing the global scaling for the energy confinement time with numerical simulations. However the scaling properties are found to brake at the local level. The boundary condition of the code has been modified to mimic the experimental Scrape-Off Layer at the plasma edge. Additional physics is now accessible, such as Kelvin-Helmholtz-like instability at separatrix and edge subcritical turbulence.
Knyhy No. 1 - 11 (1568 - 1598 rr.)
Numerical Tokamak Turbulence Project
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The primary research objective of the Numerical Tokamak Turbulence Project (NTTP) is to develop a predictive ability in modeling turbulent transport due to drift-type instabilities in the core of tokamak fusion experiments, through the use of three-dimensional kinetic and fluid simulations and the derivation of reduced models.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The primary research objective of the Numerical Tokamak Turbulence Project (NTTP) is to develop a predictive ability in modeling turbulent transport due to drift-type instabilities in the core of tokamak fusion experiments, through the use of three-dimensional kinetic and fluid simulations and the derivation of reduced models.
Numerical Tokamak Turbulence Project (OFES Grand Challenge).
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The primary research objective of the Numerical Tokamak Turbulence Project (NTTP) is to develop a predictive ability in modeling turbulent transport due to drift-type instabilities in the core of tokamak fusion experiments, through the use of three-dimensional kinetic and fluid simulations and the derivation of reduced models.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The primary research objective of the Numerical Tokamak Turbulence Project (NTTP) is to develop a predictive ability in modeling turbulent transport due to drift-type instabilities in the core of tokamak fusion experiments, through the use of three-dimensional kinetic and fluid simulations and the derivation of reduced models.