Structural analysis of W7-X: From design to assembly and operation

Bykov, V.; Schauer, F.; Egorov, K.; Eeten, P. van; Fellinger, J.; Sochor, M.; Jakšić, N.; Tereshchenko, A.; Dübner, A.; Dudek, Andrzej; Zacharias, D.; Hathiramani, D.; Czarkowski, P.; Yang, Qingxi; Bergmann, Thomas; Freundt, S.

doi:10.1016/j.fusengdes.2011.01.019

Cited by 15 publications

(30 citation statements)

References 33 publications

(40 reference statements)

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“…For D -T fuel, a temperature in the order of 10 8 K is required. A second requirement is that the product of fuel particle density n and confinement time r should be in the range of 10 14 -10 15 s/cm 3 . In magnetic confinement fusion reactors, r is approximately 1s and n is in the range of 10 14 cm -3 .…”

Section: Process Of Nuclear Fusionmentioning

confidence: 99%

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Clean and Sustainable Fusion Energy for the Future

Adelerhof¹,

Thoopal²,

Lee³

et al. 2015

PAMR

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Nuclear Fusion energy is one promising source of energy currently in the developmental stages with the potential to solve the world's energy crisis by providing a clean and almost limitless supply of energy for the entire planet. This meta-study analyses the heating systems, cooling systems, energy output, heating power input, plasma volume, economic impact, plasma temperature, plasma density, plasma confinement time and Lawson's Triple Product with respect to a variety of different nuclear fusion systems including the Wendelstein 7-X, the Helically Symmetric Stellarator Experiment, the ITER project, Joint European Torus, TFTR, IGNITOR and general information on tokamaks, stellarators as well as magnetic confinement of plasmas. Nuclear fusion is then more generally compared with four non-fusion energy sources, solar energy, wind energy, coal and hydroelectricity in terms of their overall economic impact, energy efficiency and environmental impact. Current global energy sources such as coal, oil and natural gas are briefly discussed with focus on their remaining global supply as well as their impact on the environment; this is contrasted with the remaining fuel supplies for nuclear fusion and fusion's environmental impact. The result of this metastudy was that we found that fusion power is a long term solution to the energy crisis and so more of a focus needs to be placed globally on working to expand the use of hydroelectric power. PAM Review

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Section: Process Of Nuclear Fusionmentioning

confidence: 99%

“…Wendelstein 7-X (W7-X) will be the largest stellarator in the world. Its size will be sufficient to reach reactor relevant nTτ -values [3] .…”

Section: Figurementioning

confidence: 99%

Clean and Sustainable Fusion Energy for the Future

Adelerhof¹,

Thoopal²,

Lee³

et al. 2015

PAMR

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“…Therefore, at full current, the assurance of the mechanical integrity of the central support structure (CSS), coil casings and the inter-coil support system posed a big challenge. This was investigated in detail by finite-element (FE) calculations [21,22] and a solution was found, consisting of a complex system of different support elements.…”

Section: Structural Stability Of the Superconducting Coil Systemmentioning

confidence: 99%

Technical challenges in the construction of the steady-state stellarator Wendelstein 7-X

Bosch¹,

Wolf²,

Andreeva³

et al. 2013

Nucl. Fusion

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The next step in the Wendelstein stellarator line is the large superconducting device Wendelstein 7-X, currently under construction in Greifswald, Germany. Steady-state operation is an intrinsic feature of stellarators, and one key element of the Wendelstein 7-X mission is to demonstrate steady-state operation under plasma conditions relevant for a fusion power plant. Steady-state operation of a fusion device, on the one hand, requires the implementation of special technologies, giving rise to technical challenges during the design, fabrication and assembly of such a device. On the other hand, also the physics development of steady-state operation at high plasma performance poses a challenge and careful preparation. The electron cyclotron resonance heating system, diagnostics, experiment control and data acquisition are prepared for plasma operation lasting 30 min. This requires many new technological approaches for plasma heating and diagnostics as well as new concepts for experiment control and data acquisition.

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“…The so-called narrow support elements are sliding contacts, while the lateral support elements are welded connections with the exception of the (bolted) inter-module support elements. The support concept is a compromise between stiffness and flexibility of the magnet mechanical system in order to minimize the relative movement of the coils while keeping the maximum stress values within the allowables [2]. The cold mass (coils and support system) is 425 t in total and is cooled with liquid He to 3.4 K. The cold components are in the cryostat volume which is formed by the plasma vessel, the outer vessel and the ports.…”

Section: The Devicementioning

confidence: 99%

Towards assembly completion and preparation of experimental campaigns of Wendelstein 7-X in the perspective of a path to a stellarator fusion power plant

Klinger

Baylard

Beidler

et al. 2013

Fusion Engineering and Design

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The superconducting stellarator device Wendelstein 7-X, currently under construction, is the key device for the proof of stellarator optimization principles. To establish the optimized stellarator as a serious candidate for a fusion reactor, reactor-relevant dimensionless plasma parameters must be achieved in fully integrated steady-state scenarios. After more than 10 years of construction time, the completion of the device is now approaching rapidly (mid 2014). We discuss the most important lessons learned during the device assembly and first experiences with coming major work packages. Those are (a) assembly of about 2500 large, water-cooled, 3d-shaped in-vessel component elements; (b) assembly of in total 14 superconducting current leads, one pair for each coil type, (c) assembly of the device periphery including diagnostics and heating systems. In the second part we report on the present status of planning for the first operation phase (5 − 10 s discharge duration at 8 MW heating power), the completion and hardening of the device for full power steady-state operation, and the second operation phase (up to 30 min discharge duration at 10 MW heating power). It is the ultimate goal of operation phase one to develop credible and robust discharge scenarios for the high-power steady-state operation phase two. Beyond the improved equilibrium, confinement, and stability properties owing to stellarator optimization, this requires density control, impurity control, edge iota control as well as high density microwave heating. Of paramount importance is the operation of the island divertor, which is realized in the first operation phase as an inertially cooled conventional graphite target divertor. It will be replaced later on by the steady-state capable island divertor with its water-cooled carbon fiber reinforced carbon target elements.

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Structural analysis of W7-X: From design to assembly and operation

Cited by 15 publications

References 33 publications

Clean and Sustainable Fusion Energy for the Future

Clean and Sustainable Fusion Energy for the Future

Technical challenges in the construction of the steady-state stellarator Wendelstein 7-X

Towards assembly completion and preparation of experimental campaigns of Wendelstein 7-X in the perspective of a path to a stellarator fusion power plant

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