The ARIES tokamak fusion reactor study

Najmabadi, F.; Conn, R.W.; Bartlit, J.R.; Bathke, C.G.; Beecraft, W.R.; Blanchard, James P.; Bromberg, L.; Brooks, J.N.; Cheng, E.T.; Cohn, D.R.; Cooke, P.I.H.; Creedon, R.L.; Ehst, D.A.; Emmert, G.A.; Evans, K.; Ghoniem, Nasr M.; Grotz, S.P.; Greenspan, E.; Hasan, M.Z.; Hogan, J.; Herring, J.S.; Hyatt, A.W.; Ibrahim, E.; Jardin, S.; Kernbichler, Winfried; Klasky, Marc L.; Klein, Andrew C.; Krakowski, R.A.; Kungi, T. K.; Leuer, J.A.; Mandrekas, J.; Martin, R.C.; Mau, T.K.; Miley, George H.; Miller, R.L.; Peng, Yongzheng; Reid, R. L.; Santarius, J. F.; Schaffer, M. J.; Schultz, J.H.; Schultz, Kenneth R.; Schwartz, Jacob; Sharafat, S.; Singer, Clifford E; Snead, Lance Lewis; Steiner, D.; Stricker, D.J.; Sviatoslavsky, I.N.; Sze, D.K.; Valenti, Michael; Ward, D.J.; Whitson, J. C.; Williams, J.E.C.; Wittenberg, L.J.; Wong, C.P.C.

doi:10.1109/fusion.1989.102387

Cited by 23 publications

(5 citation statements)

References 16 publications

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“…23 The COE estimated for the 1-GW(e) ARIES-I tokamak reactor has evolved from 69 mill/kW(e)h in 1988 dollars (Ref. 24) without the level of safety assurance (LSA) factors 25 appropriate to the lowactivation materials assumed, and 55 mill/kW(e)h with those credits, to 93 mill/kW(e)h in 1990 dollars (Ref. 26) without the LSA --2 credits, and 86 mill/kW(e)h with those credits.…”

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confidence: 99%

Assessment of torsatrons as reactors

Lyon¹,

Painter²

1992

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Stellarators have significant operational advantages over tokamaks as ignited steady-state reactors because stellarators have no dangerous disruptions and no need for continuous current &"ive or power recirculated to the plasma, both easing the first wall, blanket, and shield design; less severe constraints on the plasma parameters and profiles; and better access for maintenance. This study shows that a reactor based on the torsatron configuration (a stellarator variant) could also have up to double the mass utilization efficiency (MUE) and a significantly lower cost of electricity (COE) than a conventional tokamak reactor (ARIES-I) for a range of assumptions. Torsatron reactors can have much smaller coil systems than tokamak reactors because the coils are closer to the plasma and they have a smaller cross section (higher average current density because of the lower magnetic field). The reactor optimization approach and the costing and component models are those used in the current stage of the ARIES-I tokamak reactor study. Typical reactor parameters for a 1-GW(e) Compact Torsatron reactor example are major radius RO = 6.6-8.8 m, on-axis magnetic field B0 = 4.8-7.5 T, Bmax (on coils) = 16 T, MUE = 140-210 kW(e)/tonne, and COE (in constant 1990 dollars) = 67-79 mill/kW(e)h. The results are relatively sensitive to assumptions on the level of confinement improvement and the blanket thickness under the inboard half of the helical windings but relatively insensitive to other assumptions.

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confidence: 99%

Assessment of torsatrons as reactors

Lyon¹,

Painter²

1992

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“…[16,17]. Finally, there is a range of other DEMO class power plant studies performed in various nations currently and in the past, for example in US (ARIES) [18,19], Japan [20,21], Korea [22], China [23]. While this paper is not intended to be a review, we note that, for example, the ARIES studies [19] address a wide range of integration issues and give the assumptions and rationale.…”

Section: Introduction and Context-why Does Integration Mattermentioning

confidence: 99%

Towards a fusion power plant: integration of physics and technology

Morris

Akers

Cox

et al. 2022

Plasma Phys. Control. Fusion

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A fusion power plant can only exist with physics and technology acting in synchrony, over space (angstroms to tens of metres) and time (femtoseconds to decades). Recent experience with the European DEMO programme has shown how important it is to start integration early, yet go deep enough to uncover the integration impact, favourable and unfavourable, of the detailed physical and technological characteristics. There are some initially surprising interactions, for example, the fusion power density links the properties of materials in the components to the approaches to waste and remote maintenance in the context of a rigorous safety and environment regime. In this brief tour of a power plant based on a tokamak we outline the major interfaces between plasma physics and technology and engineering considering examples from the European DEMO (exhaust power handling, tritium management and plasma scenarios) with an eye on other concepts. We see how attempting integrated solutions can lead to discoveries and ways to ease interfaces despite the deep coupling of the many aspects of a tokamak plant. A power plant’s plasma, materials and components will be in new parameter spaces with new mechanisms and combinations; the design will therefore be based to a significant extent on sophisticated physics and engineering models making substantial extrapolations. There are however gaps in understanding as well as data – together these are termed “uncertainties”. Early integration in depth therefore represents a conceptual, intellectual and practical challenge, a challenge sharpened by the time pressure imposed by the global need for low carbon energy supplies such as fusion. There is an opportunity (and need) to use emerging transformational advances in computational algorithms and hardware to integrate and advance, despite the “uncertainties” and limited experimental data. We use examples to explore how an integrated approach has the potential to lead to consistent designs that could also be resilient to the residual uncertainties. The paper may stimulate some new thinking as fusion moves to the design of complete power plants alongside an evolving and maturing research programme.

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“…In the 1980s, the US temporarily impeded the large-scale tokamak studies to investigate several alternate concepts (refer to Figure 1). The tokamak studies were resumed in the early 1990s by the ARIES team, delivering a series of advanced tokamak power plants: ARIES-I [19], ARIES-II and ARIES-IV [20], ARIES-RS [21], and ARIES-AT [22]. Improvements were apparent in all designs, progressing from ARIES-I to ARIES-AT.…”

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 tokamak fusion reactor study

Cited by 23 publications

References 16 publications

Assessment of torsatrons as reactors

Assessment of torsatrons as reactors

Towards a fusion power plant: integration of physics and technology

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

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