Event Information:

• Thu

  19

  Feb

  2015

  SC Seminar: Maarten Blommaert

  11:30SC Seminar Room 32-349

  Maarten Blommaert, Forschungszentrum Jülich/SciComp

  Title:
  A Practical and in Parts Adjoint Based Gradient Computation Methodology for Efficient Optimal Magnetic Divertor Design in Nuclear Fusion Reactors

  Abstract:

  The first fusion reactor ITER is currently under construction in Cadarache, France. Meanwhile, fusion power plant conceptual design activities are intensified in Europe, US and Asia. The transition of fusion research from a purely physical science towards computational engineering is regarded as urgent in all ITER partner states.

  Design of the particle and power exhaust system, the so-called divertor configuration, is known to be a key issue to evolve from experimental fusion reactors to commercial power plants. This divertor is designed to modify the magnetic field configuration such that strong plasma flows develop towards particular high heat flux wall components of the burning chamber. However, the excessive heat loads to these components can easily exceed material limits. The divertor design process is assisted by computationally extremely demanding plasma edge codes, simulating the complex physics of the plasma edge. In order to reduce design costs, adjoint based optimal design methods have recently been introduced for divertor shape design.

  In this presentation, the focus is on the application of a similar methodology that enables adjoint based optimal design of the fusion tokomak’s magnetic configuration. However, sensitivities of the plasma edge grid generation process complicate adjoint based sensitivity calculation. We describe how these difficulties can be overcome by using a combined finite differences/continuous adjoint gradient computation. Moreover, an extensive analytical derivation of the partial derivatives of the plasma edge equations with respect to the magnetic field geometry is entirely avoided by using the finite difference approach through the forward plasma edge solver as well. Optimal design results are shown for realistic test cases on existing experimental fusion reactors.