HELIAS 5-B magnet system structure and maintenance concept

Schauer, F.; Egorov, K.; Bykov, V.

doi:10.1016/j.fusengdes.2013.01.035

Cited by 40 publications

(38 citation statements)

References 3 publications

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“…Thanks to these activities, the on-going production of the target elements is successful and allowed the fabrication of the target modules to be started. A reliable high heat flux divertor allowing the long pulse operation of W7-X is required to experimentally demonstrate and confirm the potential of the Helias stellarator line [19].…”

Section: Discussionmentioning

confidence: 99%

Summary of Research and Development Activities for the Production of the Divertor Target Elements of Wendelstein 7-X

Boscary

Peacock

Smirnow

et al. 2014

IEEE Trans. Plasma Sci.

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Abstract-The realization of the high heat flux divertor of the stellarator Wendelstein 7-X requires the production of 890 target elements. Since the divertor has to operate for 30 minutes with an input cw plasma power of 10 MW, the target elements need to be actively water-cooled. A target element is made of a CuCrZr copper alloy heat sink armored with CFC NB31 tiles. It is designed to remove a stationary heat flux of 10 MW/m² on its main area and 5 MW/m² at the end adjacent to the pumping gap. R&D activities proved to be essential for the preparation and the support of the on-going serial fabrication. The most critical issue is the stable production of the bonding between the CFC tiles and the heat sink as the divertor surface consists of about 16,000 tiles. The fast unexpected failure of one tile may reduce the whole divertor performance and, consequently, restrict the stationary machine operation. Two main R&D phases allow the design improvements of the target elements compatible with industrial and economic constrains of the series production as well as the development of quality controls such as a visual inspection system able to easily detect and fast record cracks at the interface between CFC tiles and heat sink.

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Section: Discussionmentioning

confidence: 99%

Summary of Research and Development Activities for the Production of the Divertor Target Elements of Wendelstein 7-X

Boscary

Peacock

Smirnow

et al. 2014

IEEE Trans. Plasma Sci.

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“…3. Technical drawing of a HELIAS-5B power plant concept [36]. Shown are the plasma vessel, the five different coil types, the coil support structure, the magnet system support, and the outer cryostat vessel.…”

Section: Extrapolation To a Power Plantmentioning

confidence: 99%

Wendelstein 7-X Program—Demonstration of a Stellarator Option for Fusion Energy

Wolf

Beidler

Dinklage

et al. 2016

IEEE Trans. Plasma Sci.

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The superconducting stellarator Wendelstein 7-X is currently being commissioned. First plasmas are expected for the second half of 2015. W7-X is designed to overcome the main drawbacks of the stellarator concept and simultaneously demonstrate its intrinsic advantages relative to the tokamaki.e., steady-state operation without the requirement of current drive or stability control. An elaborate optimization procedure was used to avoid excessive neoclassical transport losses at high plasma temperature, while simultaneously achieving satisfactory equilibrium and stability properties at high β in combination with a viable divertor concept. In addition, fastion confinement must be consistent with the requirements of alpha-heating in a power plant. Plasma operation of Wendelstein 7-X follows a staged approach following the successive completion of the in-vessel components. The main objective of Wendelstein 7-X is the demonstration of steady-state plasma at fusion relevant plasma parameters. Wendelstein 7-X will address major questions for the extrapolation of the concept to a power plant. These include divertor operation at high densities, plasma fueling at high central temperatures, avoiding impurity accumulation, and an assessment of the effect of neoclassical optimization on turbulent transport and fast-ion confinement. A power plant concept based on an extrapolation from Wendelstein 7-X, the helical advanced stellarator, has been developed.Index Terms-Fusion power plant, steady-state magnetic confinement, stellarator.

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“…• the sophisticated HELIAS 5-B reactor design study and its coil design are used as reference basis [9] • the coil shapes of this design are assumed to be 'fixed' but the overall size shall be scalable • based on physics principles, scaling factors and relations are introduced to flexibly scale the design according to a set of desired parameters…”

Section: Modular Coilsmentioning

confidence: 99%

“…Is should be noted here, that based on the advanced and optimised support structure design of HELIAS 5-B it is intrinsically assumed in the coil model, that the high magnetic forces and stresses on the order of 650 MPa are within allowable limits as investigated in [9,17] in detail and not treated further here.…”

Section: Modular Coilsmentioning

confidence: 99%

“…The corresponding models are described in Section 3 which include a geometry model based on Fourier coefficients, a basic island divertor model which assumes cross-field transport and high radiation, and a model for the non-planar, modular coils based on scaling aspects with respect to the HELIAS 5-B reactor design [9] in combination with analytic calculations. Furthermore, stellarator-specific plasma transport is discussed and a strategy proposed for the development of a predictive confinement time scaling.…”

Section: Introductionmentioning

confidence: 99%

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HELIAS module development for systems codes

Warmer

Beidler

Dinklage

et al. 2015

Fusion Engineering and Design

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a b s t r a c tIn order to study and design next-step fusion devices such as DEMO, comprehensive systems codes are commonly employed. In this work HELIAS-specific models are proposed which are designed to be compatible with systems codes. The subsequently developed models include: a geometry model based on Fourier coefficients which can represent the complex 3-D plasma shape, a basic island divertor model which assumes diffusive cross-field transport and high radiation at the X-point, and a coil model which combines scaling aspects based on the HELIAS 5-B reactor design in combination with analytic inductance and field calculations. In addition, stellarator-specific plasma transport is discussed. A strategy is proposed which employs a predictive confinement time scaling derived from 1-D neoclassical and 3-D turbulence simulations.This paper reports on the progress of the development of the stellarator-specific models while an implementation and verification study within an existing systems code will be presented in a separate work.This approach is investigated to ultimately allow one to conduct stellarator system studies, develop design points of HELIAS burning plasma devices, and to facilitate a direct comparison between tokamak and stellarator DEMO and power plant designs.

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HELIAS 5-B magnet system structure and maintenance concept

Cited by 40 publications

References 3 publications

Summary of Research and Development Activities for the Production of the Divertor Target Elements of Wendelstein 7-X

Summary of Research and Development Activities for the Production of the Divertor Target Elements of Wendelstein 7-X

Wendelstein 7-X Program—Demonstration of a Stellarator Option for Fusion Energy

HELIAS module development for systems codes

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