Summary of the ARIES Town Meeting: ‘Edge Plasma Physics and Plasma Material Interactions in the Fusion Power Plant Regime’

Tillack, M. S.; Turnbull, A. D.; Kessel, C.; Asakura, N.; Garofalo, A. M.; Holland, C.; Koch, F.; Linsmeier, Ch.; Lisgo, S.; Maingi, R.; Majeski, R.; Ménard, J.; Najmabadi, F.; Nygren, R.E.; Rognlien, T. D.; Ryutov, D. D.; Stambaugh, R.D.; Stangeby, P.C.; Stotler, D.P.

doi:10.1088/0029-5515/53/2/027003

Cited by 3 publications

(3 citation statements)

References 126 publications

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“…In practice, the total input power is restricted by operational beta limits and compatibility with operation at maximum field, which is not accounted for here; (2)-power density through LCFS, based on total source power and no core radiation; (3)-power through LCFS divided by major radius, based on total source power and no core radiation; (4)-figure of merit for upstream parallel heat flux density (q ), based on λ q scaling as 1/B θ ; (5)-figure of merit for upstream poloidal heat flux density (q θ ), based on λ q scaling as 1/B θ ; (6)-heat flux channel width normalized to that in ADX (6.5 T), based on multi-machine scaling for λ q [14]; (7)-SOL parallel heat flux normalized to that in ADX, based on multi-machine scaling; (8)-heat flux channel width expansion factor required to accommodate total source power while attaining less than 5 MW m −2 surface power load on two divertor targets, based on multi-machine scaling for λ q ; (9)-SOL parallel heat flux normalized to that in ADX, based on λ q scaling linear with major radius. Data taken from [4,11,14,20,37,[67][68][69][70][71][72][73][74][75][76][77][78][79][80].…”

Section: Pulse Lengthmentioning

confidence: 99%

ADX: a high field, high power density, advanced divertor and RF tokamak

LaBombard¹,

Marmar²,

Irby³

et al. 2015

Nucl. Fusion

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The MIT PSFC and collaborators are proposing a high-performance Advanced Divertor and RF tokamak eXperiment (ADX) [1]-a tokamak specifically designed to address critical needs in the world fusion research program on the pathway to DT fusion devices: 1. Demonstrate robust divertor power handling solutions at reactor-level boundary plasma parameters (heat fluxes, plasma pressures and PMI flux densities), which scale to long-pulse operation 2. Demonstrate nearly complete suppression of divertor material erosion, sufficient to sustain divertor lifetime for ~5x10 7 s of plasma exposure at reactor-level parameters 3. Achieve the above two goals while demonstrating a level of core and pedestal plasma performance that projects favorably to a fusion power plant and in physics regimes that are prototypical 4. Demonstrate efficient radio frequency current drive and heating techniques that solve plasma-material interaction challenges, scale to long-pulse operation and project to effective current profile control 5. Determine high-temperature PMI response of reactor-relevant plasma-facing material candidates, such as tungsten and liquid metals, in an integrated tokamak environment, assessing issues of material erosion, damage, material migration and fuel retention at reactor-level performance parameters. ADX is a high field (≥ 6.5 tesla, 1.5 MA), high power density facility (P/S ~ 1.5 MW/m 2) specifically designed to test innovative divertor ideas at reactor-level plasma/atomic physics parameters-divertor target plate conditions (e.g., T t < ~5eV, n t > ~10 21 m-3 [2]), boundary plasma pressures, magnetic field strengths and parallel heat flux densities entering into the divertor region-while simultaneously producing high performance core plasma conditions prototypical of a reactor: equilibrated and strongly coupled electrons and ions, regimes with low or no torque, and no fueling from external heating and current drive systems. Equally important, the experimental platform is specifically designed to test innovative concepts for lower hybrid current drive (LHCD) and ion-cyclotron range of frequency (ICRF) actuators with the unprecedented ability to deploy launch structures both on the low-magnetic-field side and the high-magnetic-field side-the latter being a location where energetic plasma-material interactions can be controlled and favorable RF wave physics leads to efficient current drive, current profile control, heating and flow drive. This triple combination-advanced divertors, advanced RF actuators, reactorprototypical core plasma conditions-will enable ADX to explore integrated solutions compatible with attaining enhanced core confinement physics, such as made possible by reversed central shear and flow drive, using only the types of external drive systems that are considered viable for a fusion power plant. Critical need-solution for heat exhaust: As stated in 2013 EFDA report [3]: "A reliable solution to the problem of heat exhaust is probably the main challenge towards the realisation of magnetic confinement fusion...

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Section: Pulse Lengthmentioning

confidence: 99%

ADX: a high field, high power density, advanced divertor and RF tokamak

LaBombard¹,

Marmar²,

Irby³

et al. 2015

Nucl. Fusion

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“…A high thermal efficiency of a power plant requires a hot coolant which results in high temperatures of the plasma-facing material, limited by recrystallization and grain growth of W. During normal operation, the divertor PFCs have to withstand 10-15 MW/m 2 steady state heat load and expected particle fluxes of $10 24 atom/m 2 s À1 [1], a few per cent of this amount consist of He from the D-T fusion reaction. The typical surface temperature of the highest heat loaded divertor plasma-facing material will be in the range between 1000 and 1700°C [2].…”

Section: Introductionmentioning

confidence: 99%

Surface morphology changes of tungsten exposed to high heat loading with mixed hydrogen/helium beams

Greuner

Maier

Balden

et al. 2014

Journal of Nuclear Materials

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“…Collisions between multiply charged ions and atomic hydrogen have received considerable interest [4][5][6][7][8]. The motivation for studying these types of collision systems is not only because of the general scientific interest but also has significant practical importance in fusion related research [9][10][11][12].…”

Section: Introductionmentioning

confidence: 99%

Target electron removal in C⁵⁺ + H collision

Atawneh

Tőkési

2021

Nucl. Fusion

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We present target ionization and charge exchange cross sections in a collision between C5+ ion and H atom. We treat the collision dynamics classically using a four-body classical trajectory Monte Carlo (CTMC) and a four-body quasi-classical Monte Carlo (QCTMC) model when the Heisenberg correction term is added to the standard CTMC model via model potential. The calculations were performed in the projectile energy range between 1.0 keV/amu and 10 MeV/amu. We found that the cross sections obtained by the QCTMC model are higher than that of the cross sections calculated by the standard CTMC model and these cross sections are closer to the previous experimental and theoretical data. Moreover, for the case of ionization, we show that the interaction between the projectile and the target electrons plays a dominant role in the enhancement of the cross sections at lower energies.

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Summary of the ARIES Town Meeting: ‘Edge Plasma Physics and Plasma Material Interactions in the Fusion Power Plant Regime’

Cited by 3 publications

References 126 publications

ADX: a high field, high power density, advanced divertor and RF tokamak

ADX: a high field, high power density, advanced divertor and RF tokamak

Surface morphology changes of tungsten exposed to high heat loading with mixed hydrogen/helium beams

Target electron removal in C⁵⁺ + H collision

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Summary of the ARIES Town Meeting: ‘Edge Plasma Physics and Plasma Material Interactions in the Fusion Power Plant Regime’

Cited by 3 publications

References 126 publications

ADX: a high field, high power density, advanced divertor and RF tokamak

ADX: a high field, high power density, advanced divertor and RF tokamak

Surface morphology changes of tungsten exposed to high heat loading with mixed hydrogen/helium beams

Target electron removal in C5+ + H collision

Contact Info

Product

Resources

About

Target electron removal in C⁵⁺ + H collision