فهرست مقالات Tokamak

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  1 - The influence of Hively and Bosch-Hale reactivities on hot ion mode in deuterium/helium-3 fuel
  Armin Taghipour S. Mohammad Motevalli Fereshteh Fadaei
  10.30495/jtap.162242
  Nowadays, there is much extensive research investigating nuclear fusion reaction with D-3He fuel as one of the most essential advanced fusion fuels. One of the most important quantities in fusion is the reactivity. In this work, with consideration of different temperatu چکیده کامل

  Nowadays, there is much extensive research investigating nuclear fusion reaction with D-3He fuel as one of the most essential advanced fusion fuels. One of the most important quantities in fusion is the reactivity. In this work, with consideration of different temperatures for ion and electron (hot ion mode), we intend to study the effects of two different reactivities (Hively and Bosch-Hale) on D-3He fusion reaction in spherical tokamaks. Accordingly, by writing the system of particle and energy balance equations for this reaction in hot ion mode, we will investigate the effects of reactivities on plasma parameters in spherical tokamaks. پرونده مقاله
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  2 - Design and fabrication of runaway probe for studying the behavior of runaway electrons in IR-T1 Tokamak
  Taher Afsari Mahmood Ghoranneviss Sakineh Meshkani Mohammad Reza Ghanbari
  10.1007/s40094-019-00366-0
  AbstractSeveral theoretical and experiential studies of runaway electrons in the well-known Tokamaks of the world have been made over the past few decades. In the present study, the measurements of runaway electrons energy were carried out by a new runaway probe in the چکیده کامل

  AbstractSeveral theoretical and experiential studies of runaway electrons in the well-known Tokamaks of the world have been made over the past few decades. In the present study, the measurements of runaway electrons energy were carried out by a new runaway probe in the IR-T1 Tokamak. In the IR-T1 Tokamak, the hard X-ray diagnostic system is used as a diagnostic global measurement system at the vessel wall of Tokamak. Runaway probe was first designed and fabricated for local measurement near the plasma edge in IR-T1 Tokamak. The new diagnostic has the advantage that the local interaction of runaways with materials can be evaluated, along with the direct measurement of the runaway electrons. The runaway probe consists of 2 LYSO (Lu 1.8Y.2SiO5:Ce) crystals covered by a graphite housing which is shielded by tungsten filter placed in the direction of runaway electrons. The main elements of the runaway probe are LYSO crystals which convert the energy of runaway electrons into visible light which is instructed to silicon photomultipliers. The present study aimed to evaluate a new runaway probe in the IR-T1 Tokamak to detect beta and gamma rays. The results indicated that electron spectrum is between 500 keV and 2 MeV at the plasma edge in the IR-T1 Tokamak. پرونده مقاله
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  3 - Mitigation of disruption on IR-T1 tokamak by means of low-energy neutral beam injection to control runaway electron generation
  M. Kafi M. Ghoranneviss M. R. Ghanbari M. K. Salem
  10.1007/s40094-020-00386-1
  AbstractIn a tokamak, the poloidal magnetic field provided by the toroidal plasma current forms an essential part of the magnetic field confining the plasma. However, instabilities of magnetohydrodynamic equilibrium can lead to an uncontrolled sudden loss of plasma curr چکیده کامل

  AbstractIn a tokamak, the poloidal magnetic field provided by the toroidal plasma current forms an essential part of the magnetic field confining the plasma. However, instabilities of magnetohydrodynamic equilibrium can lead to an uncontrolled sudden loss of plasma current and energy, which is called a disruption. Disruptions are of significant concern to future devices due to the large amount of energy released during the rapid quenching of the plasma. One important consequence of disruption is the generation of significant current carried in multi-MeV runaway electrons that are eventually lost into plasma components. They can damage the tokamak walls and its structure if they are not controlled. Disruption control by neutral beam injection has been performed on IR-T1 to study the effect on runaway electron generated by plasma disruptions. Noble gases are used for injection, pure Hydrogen, Helium and Argon. The use of these non-reactive gases for disruption control ensures they fast removed from the vessel after the termination of a tokamak discharge. A piezo-valve is used for injection which has the precision of 1 ms. The effect of runaway electron generation control during disruption is studied using a comparison between reference disruptive discharge and a discharge into which different impurity species are injected. The data collected can then be used to optimize the performance of these energetic electrons control generated in disruption. پرونده مقاله
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  4 - Application of poloidal beta and plasma internal inductance in determination of input power time of Damavand tokamak
  Ehsanallah Noori Yahya Sadeghi Mahmood Ghoranneviss
  10.1007/s40094-016-0233-9
  AbstractIn this study, magnetic measurement of poloidal fields were used to determine poloidal beta and plasma internal inductance of Damavand tokamak combination of poloidal beta and plasma internal inductance (βp+li2documentclass[12pt]{minimal} usepackage{amsmath} use چکیده کامل

  AbstractIn this study, magnetic measurement of poloidal fields were used to determine poloidal beta and plasma internal inductance of Damavand tokamak combination of poloidal beta and plasma internal inductance (βp+li2documentclass[12pt]{minimal} usepackage{amsmath} usepackage{wasysym} usepackage{amsfonts} usepackage{amssymb} usepackage{amsbsy} usepackage{mathrsfs} usepackage{upgreek} setlength{oddsidemargin}{-69pt} egin{document}$$eta _p+dfrac{l_i}{2}$$end{document}), known as Shafranov parameter, was obtained experimentally in terms of normal and tangential components of the magnetic field. Plasma internal inductance and poloidal beta were obtained using parametrization method based on analytical solution of Grad-Shafranov equation (GSE) and compared with parabolic-like profile of toroidal current density approach for determination of the plasma internal inductance. Finding evolution of βp+li2documentclass[12pt]{minimal} usepackage{amsmath} usepackage{wasysym} usepackage{amsfonts} usepackage{amssymb} usepackage{amsbsy} usepackage{mathrsfs} usepackage{upgreek} setlength{oddsidemargin}{-69pt} egin{document}$$eta _p+dfrac{l_i}{2}$$end{document} and plasma internal inductance. Finding poloidal beta (Shafranov parameter and internal inductance) and using energy balance equation, thermal energy and energy confinement were determined qualitatively in terms of poloidal beta during a regular discharge of Damavand tokamak. پرونده مقاله