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UKAEA-STEP-PR(24)122024
Ensuring tritium fuel self-sufficiency while maintaining continuous and high specification fuel flow to the tokamak via a low tritium inventory and controllable fuel cycle is a significant challenge to the STEP plant design. Effective and high-quality fuelling and exhausting is required to sustain and control a stable plasma, whereas fuel suffic…
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UKAEA-STEP-PR(24)082024
Tritiated water will be present in many demonstrator class fusion devices in a wide array of locations and concentrations. Accurate and fast measurement will be a key requirement to ensure suitable process monitoring, safety assurance and tritium tracking is in place. This work quantifies the deuterium detection limits achievable using a bench…
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UKAEA-CCFE-PR(22)052022
The analysis of quiescent discharges exhibiting edge harmonic magnetoydrodynamic activity in the JET-Carbon wall machine is presented. It is observed that the quiescent phase with multiple-n harmonic oscillations is sustained until a threshold in pedestal electron density and collisionality is crossed. The macroscopic pedestal parameters associated…
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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-PR(21)032020
DEMO is a key part of the EU fusion roadmap, where the programme is reaching the end of the pre-conceptual phase with a gate review in 2020. As part of the work to complete this phase, eight Key Design Integration Issues (KDII’s) have been identified as critical to the programme. Within KDII#1 (wall protection limiters) the feasibility of the Inn…
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UKAEA-CCFE-CP(20)852020
The anticipated heat flux limit of the European DEMO first wall is ~1MW/m2. During transient and off normal events, the heat load deposited on the wall would be much larger than that the steady state heat load and exceed the first wall limit, therefore the breeding blanket first wall needs to be protected in such events. This involves de…
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UKAEA-CCFE-PR(20)772020
Anisotropy and some limiting toroidal flow effects on the stability of non resonant ideal magnetohydrodynamic modes in hybrid shaped tokamak plasmas are investigated within the ideal MHD infernal mode framework. Such effects are found to alter the plasma magnetic well/hill, which can be interpreted as imparing the average curvature, and the stre…
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CLM P691965
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CCFE-PR(17)312015
The blanket attachment has to cope with gravity, thermal and electromagnetic loads, also it has to be installed and serviced by remote handling. Pre-stressed components suffer from stress relaxation in irradiated environments such as DEMO. To circumvent this problem pre-stressed component should be either avoided or shielded, and where possible key…
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2014
The three dimensional plasma boundary displacements induced by applied nonaxisymmetric magnetic perturbations have been measured in ASDEX Upgrade, DIII-D, JET, MAST and NSTX. The displacements arising from applied resonant magnetic perturbations (RMPs) are measured up to ±5% of the minor radius in present day machines. Good agreement can be found …
Showing 1 - 10 of 14 UKAEA Paper Results