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UKAEA-CCFE-PR(22)392022
In the absence of official standards and guidelines for nuclear fusion plants, fusion designers adopted, as far as possible, well-established standards for fission-based nuclear power plants (NPPs). This often implies interpretation and/or extrapolation, due to differences in structures, systems and components, materials, safety mitigation systems,…
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UKAEA-CCFE-PR(22)362022
There exists a large body of previous work using reduced two-dimensional models of the SOL, which model fluctuations in the drift-plane but approximate parallel transport with effective loss terms. Full size three-dimensional simulations of SOL turbulence in experimental geometries are now possible, but are far more computationally expensive than …
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UKAEA-STEP-CP(22)012022
With the ITER project entering the second half of the construction phase and various national and international plans for fusion prototype power plants being in early to advanced stages, fusion has entered the delivery era. With the urgency of the climate crisis being at the forefront of government policy agendas it is important to focus on the com…
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UKAEA-CCFE-PR(22)332022
Screening of high-Z (W) impurities from the confined plasma by the temperature gradient at the hot edge pedestal of fusion-grade H-mode plasmas has been demonstrated for the first time in the JET-ILW tokamak. Through careful optimisation of the hybrid-scenario, deuterium plasmas with sufficient heating power (≳ 32MW), high enough ion temperature …
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UKAEA-CCFE-PR(22)312022
Unusually high power loads on the Beryllium limiter caused by Neutral Beam re-ionisation, and much cooler divertor target surfaces were observed during the recent JET tritium campaign. As both phenomena are driven by scrape-off layer (SOL) physics, the SOL features of 72 tritium H-mode discharges and their deuterium references have been studied. …
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UKAEA-CCFE-PR(22)262022
All high field superconductors producing magnetic fields above 12 T are brittle. Nevertheless, they will probably be the materials of choice in commercial tokamaks because the fusion power density in a tokamak scales as the fourth power of magnetic field. Here we propose using robust, ductile superconductors during the reactor commissioning phase i…
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UKAEA-STEP-PR(22)022022
We describe a workflow that is able to approximate basic machine parameters (including but not limited to plasma current IP, major radius R0, toroidal magnetic field B0, fusion power Pfusion) based on the choice of maximum field BTF,max on the in-boa…
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UKAEA-STEP-PR(22)012022
Spherical tokamaks (STs) have been shown to possess properties desirable for a fusion power plant such as achieving high plasma β and having increased vertical stability. To understand their confinement properties in a reactor relevant regime a 1GW fusion power spherical tokamak plasma equilibrium was analysed using linear gyrokinetics to deter…
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UKAEA-CCFE-PR(25)2752021
Several fusion power concepts propose the use of liquid lithium as the primary coolant and tritium breeder. Conventional Heat Exchangers (HEX) use water. In order to avoid tritium permeation into water, a molten salt can be used as secondary coolant, with water as the tertiary system. Nevertheless, the design of the HEX to transfer the energy fr…
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UKAEA-CCFE-CP(23)392021
A key aim of the 2021 JET deuterium-tritium (D-T) experiments was to demonstrate steady high fusion power (10-15MW) with the ITER-like Be/W first wall. Plasmas were developed using D, repeated with T to investigate and mitigate isotope effects, and run with D-T to maximise fusion power. Compared with high current (q95~3) ‘baseline’ plasmas, …
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