Engineering challenges in designing an attractive compact stellarator power plant

Raffray, A.R.; El-Guebaly, L.; Ihli, T.; Malang, S.; Najmabadi, F.; Wang, X.

doi:10.1016/j.fusengdes.2007.05.023

Cited by 5 publications

(3 citation statements)

References 11 publications

(14 reference statements)

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“…This inboard shielding assumption is supported by 1D neutronics analysis described in section 4. Here, 'skeleton ring' [22] refers to an integrated support and shielding structure comprised of shield modules and manifolds to which blanket modules are attached. The skeleton-ring structure is utilized to mechanically and thermally separate the elevated-temperature core components from the colder vacuum vessel in order to withstand large loads caused by gravity, plasma disruptions and thermal expansion.…”

Section: Assessment Of Device Sizementioning

confidence: 99%

Prospects for pilot plants based on the tokamak, spherical tokamak and stellarator

et al. 2011

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A potentially attractive next-step towards fusion commercialization is a pilot plant, i.e., a device ultimately capable of small net electricity production in as compact a facility as possible and in a configuration scalable to a full-size power plant. A key capability for a pilot plant program is the production of high neutron fluence enabling fusion nuclear science and technology (FNST) research. It is found that for physics and technology assumptions between those assumed for ITER and nth-of-a-kind fusion power plant, it is possible to provide FNSTrelevant neutron wall loading in pilot devices. Thus, it may be possible to utilize a single facility to perform FNST research utilizing reactor-relevant plasma, blanket, coil, and auxiliary systems and maintenance schemes while also targeting net electricity production. In this paper three configurations for a pilot plant are considered: the advanced tokamak (AT), spherical tokamak (ST), and compact stellarator (CS). A range of configuration issues are considered including: radial build and blanket design, magnet systems, maintenance schemes, tritium consumption and self-sufficiency, physics scenarios, and a brief assessment of research needs for the configurations.

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Section: Assessment Of Device Sizementioning

confidence: 99%

Prospects for pilot plants based on the tokamak, spherical tokamak and stellarator

et al. 2011

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“…These algorithms generally focus on the magnetic őeld optimization, and don't address the later stages of design. These later stages include winding pack design, cooling system, and vacuum chamber design [Raf+07] . As these all have different functions: the winding pack must reinforce the coils, the cooling system must regulate temperature at cryogenic levels, and the vacuum chamber must be airtight and resistant to the plasma, they are generally modeled with separate codes [Raf+07].…”

Section: Introductionmentioning

confidence: 99%

“…These later stages include winding pack design, cooling system, and vacuum chamber design [Raf+07] . As these all have different functions: the winding pack must reinforce the coils, the cooling system must regulate temperature at cryogenic levels, and the vacuum chamber must be airtight and resistant to the plasma, they are generally modeled with separate codes [Raf+07]. However, an integrated design workŕow is essential because the system is space-constrained and highly interconnected.…”

Section: Introductionmentioning

confidence: 99%

Surrogate modeling for magnetic and mechanical analysis of superconducting magnets for fusion

Packman,

Riva,

Rodriguez-Fernandez

2024

Preprint

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Fusion energy has the potential to change the global energy economy and provide an essential technology to stop climate change[1]. The most promising candidates to realize a fusion power plant are tokamaks and stellarators confining the burning plasma with magnetic fields. Tokamaks are rotationally symmetric and use a large plasma current to achieve confinement. In contrast, Stellarators are non-axisymmetric and employ three-dimensionally non-planar magnetic field coils to twist the field and confine the plasma. Advantages such as disruption-free and steady-state operation [2], [3] make stellarators very attractive for such goals. Moreover, it reduces control systems issues and mitigates mechanical problems due to load cycling [4]. One of the goals of stellarator optimization is to find the best set of coils to produce the desired magnetic field. Exploring this design space requires new methods that can reduce the costly computations associated with modeling stellarator designs. This work uses Bayesian optimization, (BO) [5] which is a method that is well suited to black-box optimizations. It leverages surrogate models that are constructed to integrate as much information as possible from the available data points. This allows an optimization algorithm that significantly reduces the number of model evaluations as compared to alternative methods. This study showcases the efficacy of Bayesian optimization as a versatile tool for enhancing both magneto-static and mechanical properties within stellarator winding packs. Employing a suite of Bayesian optimization algorithms, encompassing constrained and multi-objective optimization techniques [6], [7], [8] we iteratively refine 2D and 3D models of solenoid and stellarator configurations. As fusion technology progresses from experimental stages to commercial viability, the demand for precise and efficient design methodologies escalates. By emphasizing its modularity and transferability, our approach lays the foundation for streamlining optimization processes, facilitating the integration of fusion power into a sustainable energy infrastructure.

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Divertor conceptual designs for a fusion power plant

Norajitra

Abdel‐Khalik

Giancarli

et al. 2008

Fusion Engineering and Design

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Engineering challenges in designing an attractive compact stellarator power plant

Cited by 5 publications

References 11 publications

Prospects for pilot plants based on the tokamak, spherical tokamak and stellarator

Prospects for pilot plants based on the tokamak, spherical tokamak and stellarator

Surrogate modeling for magnetic and mechanical analysis of superconducting magnets for fusion

Divertor conceptual designs for a fusion power plant

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