Taming the Heat Flux Problem: Advanced Divertors Towards Fusion Power

Kotschenreuther, M.; Mahajan, S. M.; Valanju, P.; Covele, Brent; Waelbroeck, F. L.; Canik, J.; LaBombard, B.

doi:10.1007/s10894-015-0007-4

Cited by 3 publications

(2 citation statements)

References 36 publications

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“…'snowflake' and 'Super-X' divertors, magnetic configuration with 'negative triangularity'); implementation of liquid metals (e.g. Li) as the material accommodating the heat flux and, potentially, promising a new (zero-recycling) regime of a tokamak operation, the indications of which were observed in experiments; the peculiarities of edge plasma physics in stellarators, etc (see [60][61][62][63][64][65][66][67][68][69][70][71][72][73] and the reference therein, where these topics are discussed in some detail).…”

Section: Discussionmentioning

confidence: 99%

Fascinating physics at the edge of magnetic fusion devices

Krasheninnikov¹

2022

Plasma Phys. Control. Fusion

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Physics of the processes at the edge of magnetic fusion devices is multifaceted and exhibits complex, nonlinear synergistic effects. Even though this region occupies only a small portion of the whole device, it plays a crucial role in overall plasma confinement, heat exhaust, and plasma-wall interactions. The latter affects not only the performance but also the lifetime of plasma-facing components and, therefore remains an outstanding challenge for future fusion reactors. At the edge of fusion devices, researchers are dealing with phenomena including classical and anomalous plasma transport, atomic physics effects, and physics of plasma-facing material under strong irradiation by particle and energy fluxes. Such a diversity of the edge physics makes it particularly attractive for young scientists. By working in this field, they can find endless possibilities to demonstrate their talents and creativity. This short review describes just some of the basic scrape-off layer and divertor plasma phenomena including divertor plasma detachment, intermittent bursts of anomalous cross-field plasma transport, plasma-material interactions, and dust in fusion plasmas, which are of particular interest for fusion reactors.

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Section: Discussionmentioning

confidence: 99%

Fascinating physics at the edge of magnetic fusion devices

Krasheninnikov¹

2022

Plasma Phys. Control. Fusion

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“…Kotschenreuther et al [7] and Soukhanovskii and Xu [8] review efforts to understand and optimize the divertor configuration in order to reduce target heat loads while maintaining high confinement of the fusion core. Raman et al [9] describe deep particle fueling and momentum injection using compact tori (CT) and using off-axis current drive from electron Bernstein waves (EBW) in order to optimize the performance of the steadystate advanced tokamak and spherical tokamak.…”

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confidence: 99%

Preface to the Special Issue: Strategic Opportunities for Fusion Energy

et al. 2016

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The Journal of Fusion Energy provides a forum for discussion of broader policy and planning issues that play a crucial role in energy fusion programs. In keeping with this purpose and in response to several recent strategic planning efforts worldwide, this Special Issue on Strategic Opportunities was launched with the goal to invite fusion scientists and engineers to record viewpoints of the scientific opportunities and policy issues that can drive continued advancements in fusion energy research.

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Power handling in a highly-radiative negative triangularity pilot plant

Miller,

Arnold,

Wigram

et al. 2024

Plasma Phys. Control. Fusion

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This work explores detailed power handling solutions for a class of high-field, highly-radiative negative triangularity (NT) reactors based around the MANTA concept [Rutherford et al. (2024)]. The divertor design is kept as simple as possible, opting for a standard divertor with standard leg length. FreeGS is used to create an equilibrium for the boundary region, prioritizing a short outer leg length of only ∼50 cm (∼40% of the minor radius). The UEDGE code package is used for the boundary plasma solution, to track plasma temperatures and fluxes to the divertor targets. It is found that for PSOL = 25 MW and nsep = 0.96 × 1020 m−3, conditions consistent with initial core transport modeling, little additional power mitigation is necessary. For a fixed impurity fraction of just 0.13\% Ne in the plasma, the peak heat flux density at the more heavily loaded outer targets falls to 7.8 MW/m2, while the electron temperature, Te, remains just under 5 eV. Scans around the parameter space reveal that even at densities lower than in the primary operating scenario, PSOL can be increased up to 50 MW, so long as a slightly higher fraction of extrinsic radiator is used. With less than 1% neon (Ne) impurity content, the divertor still experiences less than 10 MW/m2 at the outer target. Design of the plasma-facing components includes a close-fitting vacuum vessel with a tungsten inner surface as well as FLiBe-carrying cooling channels fashioned into the VV wall directly behind the divertor targets. For the seeded heat flux profile, Ansys Fluent heat transfer simulations estimate that the outer target temperature remains at just below 1550◦C. Initial scoping of advanced divertor designs shows that for an X-divertor, detachment of the outer target becomes much simpler, and plasma fluxes to the targets drop considerably with only 0.01% Ne content.

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Taming the Heat Flux Problem: Advanced Divertors Towards Fusion Power

Cited by 3 publications

References 36 publications

Fascinating physics at the edge of magnetic fusion devices

Fascinating physics at the edge of magnetic fusion devices

Preface to the Special Issue: Strategic Opportunities for Fusion Energy

Power handling in a highly-radiative negative triangularity pilot plant

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