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UKAEA-CCFE-PR(18)792018
This paper reports new activities conducted as part of the JET technology programme under the WP-JET3 ACT sub-project collaboration. The aim of the sub-project is to take advantage of the significant 14 MeV neutron fluence expected during JET operations to irradiate samples of materials that will used in the manufacturing of main ITER tokamak compo…
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UKAEA-CCFE-PR(18)752018
Eurofer 97 is the main structural material targeted for the DEMO reactors which will be operated under magnetic fields. It is therefore imperative to understand the effect of magnetic fields on the mechanical properties of the Eurofer 97. Here we preform 30 uniaxial tensile tests with and without a 1.5 T magnetic field at room temperature. The stat…
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UKAEA-CCFE-PR(18)772018
A novel W-based refractory high entropy alloy with outstanding radiation resistance has been developed. The alloy was grown as thin films showing a bimodal grain size distribution in the nanocrystalline and ultrafine regimes and a unique 4 nm lamella-like structure revealed by atom probe tomography (APT). Transmission electron microscopy (TEM) and …
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UKAEA-CCFE-PR(18)742018
We have implemented a one-dimensional scrape-off layer (SOL) model in the PROCESS fusion reactor systems code. It allows reactor scenarios to be obtained while limiting both the plasma temperature of the SOL at the entrance to the sheath at the divertor target, and the power density on the target. To take account of cross-field transport in an …
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UKAEA-CCFE-PR(18)732018
Alfven Eigenmodes were studied in low magnetic shear flexible heliac TJ-II (B0=0.95 T, =1.5 m, =0.22 m) NBI heated plasmas (PNBI <1.1 MW, ENBI=32 keV) by Heavy Ion Beam Probe (HIBP) [1, 2, 3]. The L-mode hydrogen plasma was investigated at various magnetic configurations with rotational transform t(a)/2
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UKAEA-CCFE-PR(18)712018
One of the overarching goals of a DEMO-class device is to demonstrate tritium self-sufficiency in a fusion power plant for the first time. A future power reactor will necessarily require a start-up inventory of tritium, mT start, before commencing fully fledged D-T operations for electricity production. In Europe, it is also presently cons…
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UKAEA-CCFE-PR(18)702018
We report results of the benchmarking of core particle transport simulations by the codes widely used in the interpretative transport analyses and predictive modelling of tokamak plasmas. Our analysis includes formulation of transport equations, difference between electron and ion particle solvers, comparison of simulations of particle sinks and so…
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UKAEA-CCFE-PR(18)692018
The impact of the three-dimensional (3D) tokamak geometry from external magnetic perturbations (MPs) on the local edge stability has been examined in high confinement mode (H-mode) plasmas with edge localised modes (ELMs) in ASDEX Upgrade. The 3D geometry has been probed using rigidly rotating MP fields. The measured distortions of the plasma bound…
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UKAEA-CCFE-PR(18)682018
Helium is widely used as a fuel or minority gas in laboratory fusion experiments, and will be present as ash in DT thermonuclear plasmas. It is therefore essential to have a good understanding of its atomic physics. To this end He II population modelling has been undertaken for the spectroscopic levels arising from shells with principal quantum…
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UKAEA-CCFE-PR(18)672018
Breeding blankets are designed to ensure tritium self-sufficiency in deuterium- tritium fusion power plants. In addition to this, breeder blankets play a vital role in shielding key components of the reactor, and provide the main source of heat which will ultimately be used to generate electricity. The design of blankets is critical to the success …
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