The ARIES-CS Compact Stellarator Fusion Power Plant

Najmabadi, F.; Raffray, A.R.; Abdel‐Khalik, S. I.; Bromberg, L.; Crosatti, L.; El-Guebaly, L.; Garabedian, P. R.; Grossman, A.; Henderson, D.; Ibrahim, Ahmad; Ihli, T.; Kaiser, T. B.; Kiedrowski, Brian C.; Ku, L. P.; Lyon, J. F.; Maingi, R.; Malang, S.; Martin, Carl J.; Mau, T. K.; Merrill, B.J.; Moore, Richard L.; Peipert, R. J.; Petti, David A.; Sadowski, D. L.; Sawan, M.E.; Schultz, J.H.; Slaybaugh, Rachel; Slattery, Kevin; Sviatoslavsky, G.; Turnbull, A. D.; Waganer, Lester M.; Wang, X. R.; Weathers, J. B.; Wilson, Paul P. H.; Waldrop, John C.; Yoda, M.; Zarnstorff, M. C.

doi:10.13182/fst54-655

Cited by 110 publications

(90 citation statements)

References 23 publications

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“…For a given set of density and temperature profiles the fusion power scales as B 4 β 2 R p 3 / A p 2 . Using the same form factors as those used in ARIES-CS [13] which is a power plant for the low aspect ratio, quasi-axisymmetric stellarators, the conditions used for the hypothetical reactor give a thermal power of about 1200 MW in a steady state.…”

Section: Transport and Confinement Propertiesmentioning

confidence: 99%

New classes of quasi-helically symmetric stellarators

Boozer

2010

Nucl. Fusion

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New classes of quasi-helically symmetric stellarators with aspect ratios ≤ 10 have been found which are stable to the perturbation of magnetohydrodynamic modes at plasma pressures of practical interest. These configurations have large rotational transform and good quality of flux surfaces. Characteristics of some selected examples are discussed in detail. The feasibility of using modular coils for these stellarators has been investigated. It is shown that practical designs for modular coils can be achieved.

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Section: Transport and Confinement Propertiesmentioning

confidence: 99%

New classes of quasi-helically symmetric stellarators

Boozer

2010

Nucl. Fusion

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“…Fast particle confinement in modern optimized designs such as W7-X and NCSX is much improved compared to conventional stellarators [30], but remains one of the main challenges for the concept. For instance, alpha confinement remained one of the most serious concerns expressed in the ARIES-CS reactor study [31], even though the ARIES design was able to reduce alpha losses to 5% over a slowing-down time.…”

Section: Energetic Ion Confinementmentioning

confidence: 99%

Recent advances in stellarator optimization

et al. 2017

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Computational optimization has revolutionized the field of stellarator design. To date, optimizations have focused primarily on optimization of neoclassical confinement and ideal MHD stability, although limited optimization of other parameters has also been performed.The purpose of this paper is to outline a select set of new concepts for stellarator optimization that, when taken as a group, present a significant step forward in the stellarator concept.One of the criticisms that has been leveled at existing methods of design is the complexity of the resultant field coils. Recently, a new coil optimization code -COILOPT++, which uses a spline instead of a Fourier representation of the coils, -was written and included in the STELLOPT suite of codes. The advantage of this method is that it allows the addition of real space constraints on the locations of the coils. The code has been tested by generating coil designs for optimized quasi-axisymmetric stellarator plasma configurations of different aspect ratios. As an initial exercise, a constraint that the windings be vertical 1 was placed on large major radius half of the non-planar coils. Further constraints were also imposed that guaranteed that sector blanket modules could be removed from between the coils, enabling a sector maintenance scheme. Results of this exercise will be presented.New ideas on methods for the optimization of turbulent transport have garnered much attention since these methods have led to design concepts that are calculated to have reduced turbulent heat loss. We have explored possibilities for generating an experimental database to test whether the reduction in transport that is predicted is consistent with experimental observations. To this end, a series of equilibria that can be made in the now latent QUASAR experiment have been identified that will test the predicted transport scalings. Fast particle confinement studies aimed at developing a generalized optimization algorithm are also discussed. A new algorithm developed for the design of the scraper element on W7-X is presented along with ideas for automating the optimization approach.

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“…Since the early 1980s, seven large-scale stellarator power plant designs have been developed in Russia, US, Germany, and Japan: RT [30], UWTOR-M [31], ASRA-6C [32], SPPS [33], ARIES-CS [34], HSR [35], and FFHR [36]. These studies vary in scope and depth and encompass a broad range of configurations, as shown in Figure 4.…”

Section: Magnetic Fusion Conceptsmentioning

confidence: 99%

Fifty Years of Magnetic Fusion Research (1958–2008): Brief Historical Overview and Discussion of Future Trends

El-Guebaly¹

2010

Energies

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Fifty years ago, the secrecy surrounding magnetically controlled thermonuclear fusion had been lifted allowing researchers to freely share technical results and discuss the challenges of harnessing fusion power. There were only four magnetic confinement fusion concepts pursued internationally: tokamak, stellarator, pinch, and mirror. Since the early 1970s, numerous fusion designs have been developed for the four original and three new approaches: spherical torus, field-reversed configuration, and spheromak. At present, the tokamak is regarded worldwide as the most viable candidate to demonstrate fusion energy generation. Numerous power plant studies (>50), extensive R&D programs, more than 100 operating experiments, and an impressive international collaboration led to the current wealth of fusion information and understanding. As a result, fusion promises to be a major part of the energy mix in the 21 st century. The fusion roadmaps developed to date take different approaches, depending on the anticipated power plant concept and the degree of extrapolation beyond ITER. Several Demos with differing approaches will be built in the US, EU, Japan, China, Russia, Korea, India, and other countries to cover the wide range of near-term and advanced fusion systems.

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The ARIES-CS Compact Stellarator Fusion Power Plant

Cited by 110 publications

References 23 publications

New classes of quasi-helically symmetric stellarators

New classes of quasi-helically symmetric stellarators

Recent advances in stellarator optimization

Fifty Years of Magnetic Fusion Research (1958–2008): Brief Historical Overview and Discussion of Future Trends

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