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VERSION:2.0
CALSCALE:GREGORIAN
PRODID:UW-Madison-Physics-Events
BEGIN:VEVENT
SEQUENCE:1
UID:UW-Physics-Event-5176
DTSTART:20190916T170500Z
DTEND:20190916T175500Z
DTSTAMP:20260415T061030Z
LAST-MODIFIED:20190917T220634Z
LOCATION:2241 Chamberlin Hall
SUMMARY:Computational approaches for nuclear design analyses of the st
 ellarator power reactor HELIAS\, Plasma Physics (Physics/ECE/NE 922) S
 eminar\, A. Haeussler\, KIT
DESCRIPTION:The Helical-Axis Advanced Stellarator (HELIAS) is the lead
 ing stellarator concept in Europe and developed at the Max-Planck-Inst
 itute for Plasma Physics (IPP)\, Greifswald\, Germany. Based on the 5-
 field-period symmetry\, the HELIAS-5B engineering design study emerged
  which aims at a stellarator power reactor designed for 3000 MW fusion
  power.
\n
\nThe stellarator confines hot plasma only by external supe
 rconducting field coils\, which are very sensitive for the neutron flu
 x\, leading to a complex 3D topology of the magnetic configuration. Th
 ese coils define the shape of the device and limit the space available
  outside the plasma chamber for the vacuum vessel and the in-vessel co
 mponents required for breeding\, shielding and heat removal.
\n
\nThe 
 neutronic performance of the HELIAS fusion reactor needs to be assesse
 d. This requires a suitable computational approach to simulate the gen
 eration of source neutrons in the plasma chamber and the neutron trans
 port through the complex HELIAS geometry. The approach is based on the
  Monte Carlo (MC) particle transport technique applied with the Direct
  Accelerated Geometry Monte Carlo (DAGMC) method. Beside the neutron s
 ource is a suitable geometry description important to represent a simp
 lified HELIAS geometry as good as possible in the simulation. For the 
 first neutronic design analyses\, like neutron wall loading\, tritium 
 breeding ratio\, neutron flux distribution and shielding performance\,
  a simplified HELIAS model with homogenized material for each function
 al layer is used.
\n
\nThe talk will present the development of the st
 ellarator neutron source based on plasma physics simulation\, challeng
 es in CAD to MC geometry translation including different translation a
 pproaches\, first neutronic design analyses and the shielding performa
 nce in comparison to the design values specified as limits for the rad
 iation loads to the superconducting toroidal field coils of the DEMO t
 okamak.
URL:https://www.physics.wisc.edu/events/?id=5176
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