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UKAEA-CCFE-PR(22)172022
As the international tokamak ITER is being built, non-linear MHD simulations are playing an essential role in active research, understanding, and prediction of tokamak plasmas for the realisation of a fusion power plant. The development of MHD codes like JOREK is a key aspect of this research effort, and provides invaluable insight into the plasma …
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UKAEA-CCFE-PR(22)112022
Solid titanium beryllide blocks will be used for neutron multiplication in the in the helium-cooled pebble bed (HCPB) blanket concept of EU DEMO. A combination of hot extrusion of Be-Ti powders and subsequent hot isostatic pressing (HIP) of the obtained Be-Ti composites has been proposed for manufacturing such blocks. This work is devoted to the st…
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UKAEA-CCFE-PR(22)082022
MAST-U has recently started operating with a Super-X divertor, designed to increase total flux expansion and neutral trapping, both predicted through simple analytic models and SOLPS calculations to reduce the plasma and impurity density detachment thresholds. In this study, utilising the SOLPS-ITER code, we are quantifying the possible gain allowe…
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UKAEA-CCFE-PR(22)072022
Self-ion irradiation of pure tungsten with 2 MeV W ions provides a way of simulating microstructures generated by neutron irradiation in tungsten components of a fusion reactor. Electron microscopy has been used to characterize defects formed in tungsten samples by ion irradiation and estimate their density and size distribution. Some of the sample…
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UKAEA-RACE-PR(22)012022
Supervising and controlling remote robot systems currently requires many specialised operators to have knowledge of the internal state of the system in addition to the environment. For applications such as remote maintenance of future nuclear fusion reactors, the number of robots (and hence supervisors) required to maintain or decommission a fac…
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UKAEA-CCFE-PR(22)042022
The small punch test (SPT) has been widely used to evaluate the mechanical properties of materials for the nuclear industry due to its advantage of requiring minimal sample volumes. In this paper, the correlation between SPT and uniaxial tensile testing (UTT) is investigated for three materials used in the plasma-facing components of fusion reactor…
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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-PR(24)2372021
Control of the detachment front between the target and the X-point is necessary for minimizing the effect of detachment on the core plasma (core radiation and loss of confinement) and maximizing the divertor functions (reduction of target heat load and sputtering, He pumping). However, such control has been difficult in experiments. The SOLPS-IT…
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UKAEA-CCFE-CP(23)582021
Erbium hydrides are suitable materials for the long-term storage of hydrogen and this work details the first reported instance of erbium deuteride synthesis via ion beam implantation. This method offers an alternative loading methodology to conventional gas loading with several advantages and these are discussed within. The work also briefly dis…
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UKAEA-RACE-CP(23)032021
This paper reports on a study of the existing or proposed maintenance arm systems with similar functions and structure to that of the proposed DEMO Multi-Purpose Deployer (MPD).The current MPD design iteration consists of a boom deployment system that is ~30m long and can support a payload of ~1000kg, while still being able to access the DEMO va…
Showing 141 - 150 of 438 UKAEA Paper Results