Kinetic Simulations of Ion Transport in Fusion Devices

  • Andrés de Bustos Molina

Part of the Springer Theses book series (Springer Theses)

Table of contents

  1. Front Matter
    Pages i-xi
  2. Andrés de Bustos Molina
    Pages 1-27
  3. Andrés de Bustos Molina
    Pages 29-46
  4. Andrés de Bustos Molina
    Pages 47-61
  5. Andrés de Bustos Molina
    Pages 63-95
  6. Andrés de Bustos Molina
    Pages 97-109
  7. Andrés de Bustos Molina
    Pages 111-114
  8. Back Matter
    Pages 115-128

About this book


This thesis deals with the problem of ion confinement in thermonuclear fusion devices. It is a topic of general interest, as it helps to understand via numerical simulations the ion confinement properties in complex geometries, in order to predict their behavior and maximize the performance of future fusion reactors. The main work carried out in this thesis is the improvement and exploitation of an existing simulation code called ISDEP.  This code solves the so-called ion collisional transport in arbitrary plasma geometry, improving in this sense other existing codes. Additionally, it presents outstanding portability and scalability in distributed computing architectures, such as Grid or Volunteer Computing.
The main physical results can be divided into two blocks. First, the study of 3D ion transport in ITER is presented. ITER is the largest fusion reactor (under construction) and most of the simulations so far assume the axis-symmetry of the device. Unfortunately, this symmetry is only an approximation because of the discrete number of magnetic coils used. ISDEP has shown, using a simple model of the 3D magnetic field, how the ion confinement is affected by this symmetry breaking.
Secondly, ISDEP has been applied successfully to the study of fast ion dynamics in fusion plasmas. The fast ions, with energies much larger than the thermal energy, are a product of the device’s heating system. Thus, a numerical predictive tool can be used to improve the heating efficiency. ISDEP has been combined with the FAFNER2 code to study such ions in stellarator (TJ-II, LHD) and tokamak (ITER) geometries. It has also been validated by experimental results. In particular, comparisons with the CNPA diagnostic in the TJ-II stellarator are remarkable.


3D Ion Transport 3D Ion Transport in ITER Applying ISDEP Confinement in Complex Geometries Confinement in Fusion Devices ITER Simulations Ion Collisional Transport Ion Dynamics in Fusion Plasmas Prediction of Confinement Properties Simulation of Fusion Processes

Authors and affiliations

  • Andrés de Bustos Molina
    • 1
  1. 1.TokamaktheorieMax Planck Institute für PlasmaphysikGarching bei MünchenGermany

Bibliographic information

  • DOI
  • Copyright Information Springer International Publishing Switzerland 2013
  • Publisher Name Springer, Cham
  • eBook Packages Physics and Astronomy
  • Print ISBN 978-3-319-00421-1
  • Online ISBN 978-3-319-00422-8
  • Series Print ISSN 2190-5053
  • Series Online ISSN 2190-5061
  • Buy this book on publisher's site