Abstract
Full text: The Helias reactor (HSR) is an upgraded version of the Wendelstein 7-X experiment,which is under construction in the city of Greifswald.The dimensions of the Helias reactor are determined by the need to accomodate a blanket and a shield between coils and plasma The main data are:major radius 22 m, av. plasma radius 1.8 m, magnetic field on axis 5 T, maximum field on coils 10 T. The rotational transform is in the range of {iota} =0.84 -1.0. Islands at the plasma edge are utilized for divertor- action. Recent studies have been focussed on a 4-period Helias configuration (major radius 18 m, plasma radius 2.0 m,B =5 T), which presents a more compact option than the five period configuration.The modular coil system comprises 40 coils, which are constructed using NbTi-superconducting cables. Efforts have been made to reduce the maximum magnetic field in the coils to 10.3 T by shaping the winding pack trapezoidally. For this reason the winding pack consists of 8 double pancakes,which are wound on a mould and then welded together. The ANSYS-code is the main tool to compute the stress distribution in the coils and in the support system. Several blanket concepts, the liquid LiPb-breeder and
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Beidler, C D;
Harmeyer, E;
Herrnegger, F;
Igitkhanov, Y;
Kisslinger, J;
Nuehrenberg, C;
Sidorenko, I;
Turkin, Y;
Wobig, H
[1]
- Max-Planck Institut fuer Plasmaphysik, Garching (Germany). EURATOM Association
Citation Formats
Beidler, C D, Harmeyer, E, Herrnegger, F, Igitkhanov, Y, Kisslinger, J, Nuehrenberg, C, Sidorenko, I, Turkin, Y, and Wobig, H.
Recent development in Helias reactor studies.
Australia: N. p.,
2002.
Web.
Beidler, C D, Harmeyer, E, Herrnegger, F, Igitkhanov, Y, Kisslinger, J, Nuehrenberg, C, Sidorenko, I, Turkin, Y, & Wobig, H.
Recent development in Helias reactor studies.
Australia.
Beidler, C D, Harmeyer, E, Herrnegger, F, Igitkhanov, Y, Kisslinger, J, Nuehrenberg, C, Sidorenko, I, Turkin, Y, and Wobig, H.
2002.
"Recent development in Helias reactor studies."
Australia.
@misc{etde_20410093,
title = {Recent development in Helias reactor studies}
author = {Beidler, C D, Harmeyer, E, Herrnegger, F, Igitkhanov, Y, Kisslinger, J, Nuehrenberg, C, Sidorenko, I, Turkin, Y, and Wobig, H}
abstractNote = {Full text: The Helias reactor (HSR) is an upgraded version of the Wendelstein 7-X experiment,which is under construction in the city of Greifswald.The dimensions of the Helias reactor are determined by the need to accomodate a blanket and a shield between coils and plasma The main data are:major radius 22 m, av. plasma radius 1.8 m, magnetic field on axis 5 T, maximum field on coils 10 T. The rotational transform is in the range of {iota} =0.84 -1.0. Islands at the plasma edge are utilized for divertor- action. Recent studies have been focussed on a 4-period Helias configuration (major radius 18 m, plasma radius 2.0 m,B =5 T), which presents a more compact option than the five period configuration.The modular coil system comprises 40 coils, which are constructed using NbTi-superconducting cables. Efforts have been made to reduce the maximum magnetic field in the coils to 10.3 T by shaping the winding pack trapezoidally. For this reason the winding pack consists of 8 double pancakes,which are wound on a mould and then welded together. The ANSYS-code is the main tool to compute the stress distribution in the coils and in the support system. Several blanket concepts, the liquid LiPb-breeder and the ceramic breeder have been adapted to the Helias geometry. Power deposition in the blanket segments is roughly a factor two smaller than in an equivalent tokamak with the same fusion power. As a consequence,the lifetime of first wall and blanket components is nearly twice as long as in a tokamak reactor. Presently a water-cooled LiPb- blanket is favoured in comparison with ceramic breeders, since safety properties and maintenance procedure seem to be more advantageous in this concept. Maintenance and replacement of blanket segments through portholes have also been studied with respect to its geometric compatibility. First results of neutronic calculations using the MCNP code demonstrate the impact of the geometry on the wall loading and the breeding factor. The following issues are being addressed by the physics studies: plasma equilibrium and MHD-stability; neoclassical transport in the Helias configuration; start-up scenarios and steady state burn; Alpha particle physics; modelling the fusion plasma using empirical scaling laws; divertor physics. The paper discusses the various aspects of the 4-period configuration, in particular, its potential as a power plant. Special attention will be given to a 4-period version as an ignition experiment, which is defined by self-sustaining burn at a minimum of fusion power. Copyright (2002) Australian National University- Research School of Physical Sciences and Engineering.}
place = {Australia}
year = {2002}
month = {Jul}
}
title = {Recent development in Helias reactor studies}
author = {Beidler, C D, Harmeyer, E, Herrnegger, F, Igitkhanov, Y, Kisslinger, J, Nuehrenberg, C, Sidorenko, I, Turkin, Y, and Wobig, H}
abstractNote = {Full text: The Helias reactor (HSR) is an upgraded version of the Wendelstein 7-X experiment,which is under construction in the city of Greifswald.The dimensions of the Helias reactor are determined by the need to accomodate a blanket and a shield between coils and plasma The main data are:major radius 22 m, av. plasma radius 1.8 m, magnetic field on axis 5 T, maximum field on coils 10 T. The rotational transform is in the range of {iota} =0.84 -1.0. Islands at the plasma edge are utilized for divertor- action. Recent studies have been focussed on a 4-period Helias configuration (major radius 18 m, plasma radius 2.0 m,B =5 T), which presents a more compact option than the five period configuration.The modular coil system comprises 40 coils, which are constructed using NbTi-superconducting cables. Efforts have been made to reduce the maximum magnetic field in the coils to 10.3 T by shaping the winding pack trapezoidally. For this reason the winding pack consists of 8 double pancakes,which are wound on a mould and then welded together. The ANSYS-code is the main tool to compute the stress distribution in the coils and in the support system. Several blanket concepts, the liquid LiPb-breeder and the ceramic breeder have been adapted to the Helias geometry. Power deposition in the blanket segments is roughly a factor two smaller than in an equivalent tokamak with the same fusion power. As a consequence,the lifetime of first wall and blanket components is nearly twice as long as in a tokamak reactor. Presently a water-cooled LiPb- blanket is favoured in comparison with ceramic breeders, since safety properties and maintenance procedure seem to be more advantageous in this concept. Maintenance and replacement of blanket segments through portholes have also been studied with respect to its geometric compatibility. First results of neutronic calculations using the MCNP code demonstrate the impact of the geometry on the wall loading and the breeding factor. The following issues are being addressed by the physics studies: plasma equilibrium and MHD-stability; neoclassical transport in the Helias configuration; start-up scenarios and steady state burn; Alpha particle physics; modelling the fusion plasma using empirical scaling laws; divertor physics. The paper discusses the various aspects of the 4-period configuration, in particular, its potential as a power plant. Special attention will be given to a 4-period version as an ignition experiment, which is defined by self-sustaining burn at a minimum of fusion power. Copyright (2002) Australian National University- Research School of Physical Sciences and Engineering.}
place = {Australia}
year = {2002}
month = {Jul}
}