The mega amp spherical tokamak

Meyer, H.

doi:10.1016/b978-0-08-100315-2.00012-x

Cited by 2 publications

(2 citation statements)

References 188 publications

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“…Spherical Tokamak for Energy Production (STEP) [1,2] is a prototype fusion power plant planned to be built in the UK * Author to whom any correspondence should be addressed.…”

Section: Introductionmentioning

confidence: 99%

First SOLPS-ITER predictions of the impact of cross-field drifts on divertor and scrape-off layer conditions in double-null configuration of STEP

Karhunen,

Henderson,

Järvinen

et al. 2024

Nucl. Fusion

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Introduction of cross-field drifts in SOLPS-ITER simulations of connected double-null plasmas in STEP with the ion ∇B×B drift towards the upper divertors was found to enhance the detachment of the inner divertors with decreased target densities and ion and heat fluxes, while simultaneously complicating the access to detachment in the outer lower divertor by increasing the target temperature and heat loads to levels above the engineering limits.The ∇B×B drift was observed to significantly affect the radial heat transport between the core and the scrape-off layer (SOL), altering the poloidal temperature and pressure profiles and, consequently, the poloidal conductive and convective heat transport in the SOL. As a result, up-down asymmetries of 52:48 and 58:42 biased towards the outer lower and upper inner divertors, respectively, were observed to arise in the unmitigated power entering the divertor regions, breaking the up-down symmetry seen in simulations without the drift terms and contradicting with earlier experimental observations on the low-field side. Moreover, the upstream electron density was found to decrease noticeably in the core and separatrix regions following the activation of the drifts due to an increased share of the neutrals arriving from D2 injections near the upper and lower X-points ionizing already in the private flux regions.

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“…Spherical Tokamak for Energy Production (STEP) [1,2] is a prototype fusion power plant planned to be built in the UK * Author to whom any correspondence should be addressed.…”

Section: Introductionmentioning

confidence: 99%

First SOLPS-ITER predictions of the impact of cross-field drifts on divertor and scrape-off layer conditions in double-null configuration of STEP

Karhunen,

Henderson,

Järvinen

et al. 2024

Nucl. Fusion

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“…In a major drive to further the development of nuclear fusion as a viable energy source for the future, the UK is putting significant resources into the 'Spherical Tokamak for Energy Production' (STEP) project [1][2][3]. This project aims at building a prototype fusion power plant by ∼2040.…”

Section: Introductionmentioning

confidence: 99%

Plasma control for the step prototype power plant

Lennholm,

Aleiferis,

Bakes

et al. 2024

Nucl. Fusion

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In 2019 the UK launched the STEP programme to design and build a prototype electricity producing nuclear fusion power plant, aiming to start operation around 2040. The plant should lay the foundation for the development of commercial nuclear fusion power plants. The design is based on the spherical tokamak principle, which opens a route to high pressure, steady state, operation. While facilitating steady state operation, the spherical design introduces some specific plasma control challenges: i) All plasma current during the burn phase should to be generated through non-inductively means, dominated by bootstrap current. This leads to operation at high normalised plasma pressure β_"N" with high plasma elongation, which in turn imposes effective active stabilisation of the vertical plasma position. ii) The tight aspect ratio means very limited space for a central solenoid, imposing that even the current ramp up must be non-inductively generated. iii) The compact design leads to extreme heat loads on plasma facing components. A double null design has been chosen to spread this load, putting strict demands on the control of the unstable vertical plasma position. iv) The heat pulses associated with unmitigated ELMs are unlikely to be unacceptable imposing ELM free operation or active ELM control. v) To reduce and spread heat loads, core and divertor radiation and momentum loss has to be controlled, aiming to operate with simultaneously detached upper and lower divertors. vi) High pressure operation is likely to require active resistive wall mode stabilisation. vii) The conductivity distribution in structures near the plasma must be carefully selected to reduce the growth rates for the vertical instability and the resistive wall mode without damping the penetration of the of magnetic fields from active control coils too much. This article describes the initial work carried out to develop a STEP plasma control system.

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The mega amp spherical tokamak

Cited by 2 publications

References 188 publications

First SOLPS-ITER predictions of the impact of cross-field drifts on divertor and scrape-off layer conditions in double-null configuration of STEP

First SOLPS-ITER predictions of the impact of cross-field drifts on divertor and scrape-off layer conditions in double-null configuration of STEP

Plasma control for the step prototype power plant

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