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

## Abstract

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.

- Authors:

- Radiation Application Department, Shahid Beheshti University, Tehran (Iran, Islamic Republic of)
- Nuclear Safety and Radiological Protection Group, Nuclear Science and Technology Research Institute, Tehran (Iran, Islamic Republic of)

- Publication Date:

- OSTI Identifier:
- 22599941

- Resource Type:
- Journal Article

- Resource Relation:
- Journal Name: Physics of Plasmas; Journal Volume: 23; Journal Issue: 8; Other Information: (c) 2016 Author(s); Country of input: International Atomic Energy Agency (IAEA)

- Country of Publication:
- United States

- Language:
- English

- Subject:
- 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; 71 CLASSICAL AND QUANTUM MECHANICS, GENERAL PHYSICS; ACCURACY; ANALYTICAL SOLUTION; CALCULATION METHODS; COMPARATIVE EVALUATIONS; EQUILIBRIUM; ERRORS; GRAD-SHAFRANOV EQUATION; INTERPOLATION; ITER TOKAMAK; MAGNETIC FIELDS; NONLINEAR PROBLEMS; NSTX DEVICE; PLASMA; PLASMA CONFINEMENT; TWO-DIMENSIONAL CALCULATIONS

### Citation Formats

```
Rasouli, C., Abbasi Davani, F., and Rokrok, B..
```*Study of plasma equilibrium in toroidal fusion devices using mesh-free numerical calculation method*. United States: N. p., 2016.
Web. doi:10.1063/1.4960680.

```
Rasouli, C., Abbasi Davani, F., & Rokrok, B..
```*Study of plasma equilibrium in toroidal fusion devices using mesh-free numerical calculation method*. United States. doi:10.1063/1.4960680.

```
Rasouli, C., Abbasi Davani, F., and Rokrok, B.. Mon .
"Study of plasma equilibrium in toroidal fusion devices using mesh-free numerical calculation method". United States.
doi:10.1063/1.4960680.
```

```
@article{osti_22599941,
```

title = {Study of plasma equilibrium in toroidal fusion devices using mesh-free numerical calculation method},

author = {Rasouli, C. and Abbasi Davani, F. and Rokrok, B.},

abstractNote = {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.},

doi = {10.1063/1.4960680},

journal = {Physics of Plasmas},

number = 8,

volume = 23,

place = {United States},

year = {Mon Aug 15 00:00:00 EDT 2016},

month = {Mon Aug 15 00:00:00 EDT 2016}

}