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UKAEA-CCFE-PR(21)252021
We present modifications of the systems code Process that allow for a description of a general class of stellarator power plants, based on a stellarator coil-set and the respective MHD plasma equilibrium. For this, we modify Process such that each stellarator confi…
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UKAEA-RACE-CP(21)032021
Driving energy consumption plays a major role in mobile robots navigating challenging environments, especially if they are left to operate unattended under limited on-board power. This paper reports on first results of an energy-aware path planner, which can provide estimates of the driving energy consumption and energy recovery of a robot traversi…
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UKAEA-CCFE-PR(21)192021
A novel high-performance computing algorithm, developed in response to the next generation of computational challenges associated with burning plasma regimes in ITER-scale tokamak devices, has been tested and is described herein. LOCUST-GPU 2 The Lorentz-Orbit Code for Use in Stellarators and Tokamaks (LOCUST) is designed for computationally scal…
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UKAEA-RACE-CP(21)012021
In order to reach commercially-relevant availability future fusion power plants must have highly efficient maintenance systems. On the other hand, as radiation levels increase so too will the number of maintenance tasks that must be performed without human access. To meet these conflicting constraints remote maintenance systems must significantly…
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UKAEA-CCFE-CP(21)032021
The field of fusion energy is about to enter the ITER era, for the first time we will have access to a device capable of producing 500 MW of fusion power, with plasmas lasting more than 300 seconds and with core tem- perature…
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UKAEA-CCFE-PR(21)142021
As a demonstration fusion power plant, EU DEMO has to prove the maturity of fusion technology and its viability for electricity production. The central requirements for DEMO rest on its capability to generate significant net electric power to the grid (300MW to 500 MW) safely and consistently. Plant availability and lifetime will approach that of a…
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UKAEA-CCFE-PR(21)112021
The SOLPS-ITER simulations of European DEMO reactor, with 450 MW of power to be exhausted, show an increased operational space compared to the conventional single-null configuration. Using a reduced model with fluid neutrals and bundled impurities, we assessed the existence and the boundaries of operational space for DEMO with the conventional sing…
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UKAEA-CCFE-PR(21)102021
The divertor target plates are the most exposed in-vessel components to high heat flux loads in a fusion reactor due to a combination of plasma bombardment, radiation and nuclear heating. Reliable exhaust systems of such a huge thermal power required a robust and durable divertor target with a sufficiently large heat removal capability and lifetime…
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UKAEA-CCFE-PR(21)082021
A survey of the correlation between temperature and density gradient lengths ( and ) has been performed for the near SOL regions in the ASDEX Upgrade tokamak. In common with previous studies, the near SOL temperature and density gradient length ratio, , is found to be close to unity across a wide range of plasmas. However, it is found that it is po…
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UKAEA-CCFE-PR(21)032021
The resistive wall mode (RWM) control on the HL-2M tokamak is simulated with the MARS-F code [Liu Y Q et al 2000 Phys. Plasmas 7 3681], aiming at quantifying control current and voltage requirements when more realistic issues are taken into account, i.e. the control power saturation and the sensor signal noise. The fluid model predicts a narrow st…
Showing 131 - 140 of 500 UKAEA Paper Results