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UKAEA-CCFE-CP(18)032018
Recent results from MAST address key physics issues for ITER operations and the design of future devices, by advancing our understanding of through analysis of high-resolution data and numerical modelling. Modelling of the interaction between filaments with BOUT++ indicates filaments separated by more than 5x their width move independently, and …
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UKAEA-CCFE-PR(18)652018
During the 2015-2016 JET campaigns many efforts have been devoted to the exploration of high-performance plasma scenarios envisaged for DT operation in JET. In this paper we review various key recent hybrid discharges and model the combined ICRF+NBI heating. These deuterium discharges with deuterium beams had the ICRF antenna frequency tuned to mat…
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UKAEA-CCFE-PR(18)832018
Magnetic plasma confinement is a key element of fusion tokamak power plant design, yet changes in magnetic properties of alloys and steels occurring under neutron irradiation are often overlooked. We perform a quantitative study exploring how irradiation-induced precipitation affects magnetic properties of Fe-Cr alloys. Magnetic properties are simu…
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UKAEA-CCFE-PR(19)072018
Ray-tracing techniques are applied to divertor filtered imaging, a diagnostic that has long been plagued by polluting reflected light features in metal walled fusion machines. A physically realistic surface reflection model is developed from a Cook-Torrence microfacet BRDF model. Camera calibration images of in-vessel point lights at JET are use…
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UKAEA-CCFE-PR(18)822018
Recent experiments on TCV have made significant progress toward partial detachment of the outer divertor in neutral beam heated H-mode plasmas. The heating power required to enter H-mode was measured in a range of divertor configurations, finding that, in the vicinity of the PL-H/ne curve, the threshold power is largely independent of the poloidal …
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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)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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UKAEA-CCFE-PR(18)532018
Within a tokamak fusion energy device, the performance and lifespan of a divertor monoblock under high heat flux cycles is of particular interest. Key to this is the quality of manufacture, especially the material joining interfaces. Presented here is a comparative study between X-ray and neutron tomography to investigate the quality of manufacture…
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UKAEA-CCFE-PR(19)032018
A new 1D divertor plasma code, SD1D, has been used to examine the role of recombination, radiation, and momentum exchange in detachment. Neither momentum or power losses by themselves are found to be sufficient to produce target ion flux rollover in detachment; radiative power losses are required to a) limit and reduce the ionization source and …
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UKAEA-CCFE-PR(18)502018
There are many sources of random and systematic error in composition quantification by atom probe, however, often only statistical error is reported. Identification of ions and overlaps or interferences of peaks in the mass spectrum are one major source of uncertainty much larger than counting error. These overlaps can be solved using maximum likel…
Showing 211 - 220 of 353 UKAEA Paper Results