Study of plasma equilibrium in toroidal fusion devices using mesh-free numerical calculation method

Plasma confinement using external magnetic field is one of the successful ways leading to the controlled nuclear fusion. Development and validation of the solution process for plasma equilibrium in the experimental toroidal fusion devices is the main subject of this work. Solution of the nonlinear 2...

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Bibliographic Details
Published inPhysics of plasmas Vol. 23; no. 8
Main Authors Rasouli, C., Abbasi Davani, F., Rokrok, B.
Format Journal Article
LanguageEnglish
Published Melville American Institute of Physics 01.08.2016
Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
ACCURACY
ANALYTICAL SOLUTION
CALCULATION METHODS
CLASSICAL AND QUANTUM MECHANICS, GENERAL PHYSICS
COMPARATIVE EVALUATIONS
Domains
EQUILIBRIUM
Equilibrium equations
Error analysis
ERRORS
GRAD-SHAFRANOV EQUATION
INTERPOLATION
ITER TOKAMAK
MAGNETIC FIELDS
Mathematical analysis
Meshless methods
NONLINEAR PROBLEMS
NSTX DEVICE
Nuclear fusion
PLASMA
PLASMA CONFINEMENT
Plasma equilibrium
Plasma physics
Tokamak devices
TWO-DIMENSIONAL CALCULATIONS
Vacuum chambers
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Summary:Plasma confinement using external magnetic field is one of the successful ways leading to the controlled nuclear fusion. Development and validation of the solution process for plasma equilibrium in the experimental toroidal fusion devices is the main subject of this work. Solution of the nonlinear 2D stationary problem as posed by the Grad-Shafranov equation gives quantitative information about plasma equilibrium inside the vacuum chamber of hot fusion devices. This study suggests solving plasma equilibrium equation which is essential in toroidal nuclear fusion devices, using a mesh-free method in a condition that the plasma boundary is unknown. The Grad-Shafranov equation has been solved numerically by the point interpolation collocation mesh-free method. Important features of this approach include truly mesh free, simple mathematical relationships between points and acceptable precision in comparison with the parametric results. The calculation process has been done by using the regular and irregular nodal distribution and support domains with different points. The relative error between numerical and analytical solution is discussed for several test examples such as small size Damavand tokamak, ITER-like equilibrium, NSTX-like equilibrium, and typical Spheromak.
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ISSN:1070-664X
1089-7674
DOI:10.1063/1.4960680