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UKAEA-CCFE-PR(23)1702023
Neutral Beam Injection (NBI) is a flexible auxiliary heating method for tokamak plasmas, capable of being efficiently coupled to the various plasma configurations required in the Tritium and mixed DeuteriumTritium Experimental campaign (DTE2) on the JET device. High NBI power was required for high fusion yield and alpha particle studies and to …
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UKAEA-CCFE-PR(23)1652023
This work studies the interaction between Radio Frequency (RF) waves used for Ion Cyclotron Resonance Heating (ICRH) and the fast D and T Neutral Beam Injected (NBI) ions in DT plasma. The focus is on the effect of this interaction, also referred to as synergistic effects, on the fusion performance in the recent JET DTE2 campaign. Experimental d…
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UKAEA-CCFE-PR(23)1392023
Refractory high-entropy alloys (RHEAs) with high melting points and low neutron absorption cross-section are sought for generation-IV fission and fusion reactors. A high throughput computational screening tool, Alloy Search and Predict (ASAP), was used to identify promising RHEA candidates from over 1 million four-element equimolar combinations. Th…
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UKAEA-CCFE-PR(23)1252023
In JET deuterium-tritium (D-T) plasmas, the fusion power is produced through thermonuclear reactions and reactions between thermal ions and fast particles generated by neutral beam injection (NBI) heating or accelerated by electromagnetic wave heating in the ion cyclotron range of frequencies (ICRF). To complement the experiments with 50/50 D/T …
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UKAEA-CCFE-PR(23)1212023
In the paper we present an overview of interpretive modelling of a database of JET-ILW 2021 D-T discharges using the TRANSP code. Our main aim is to assess our capability of computationally reproducing the fusion performance of various D-T plasma scenarios using different external heating and D-T mixtures, and understand the performance driving mec…
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UKAEA-CCFE-PR(23)132023
Following the first Deuterium-Tritium Experiment (DTE1) at UKAEA, modifications were investigated to the Joint European Torus’ (JET) gas introduction systems to increase the gas feed capabilities of the JET facility to better support future campaigns. The gas introduction systems comprise the gas introduction and gas distribution system (GI/GD)…
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UKAEA-CCFE-CP(23)542022
Several Ion Cyclotron Resonance Heating (ICRH) schemes in DT plasma have been considered for the ITER reactor [1]. Most of these heating schemes are minority heating at fundamental frequency. In DT plasma, both reactants can also absorb RF power as majorities at fundamental n=1 or harmonic n=2 frequency. Understanding benefits of directly heatin…
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UKAEA-RACE-CP(22)012022
The Active Cells Facility will be the world’s largest hot cell and will be used to process radioactive waste generated in the operation of the European Spallation Source. Several innovative technologies and approaches have been developed for the ESS Active Cells, drawing on advances made in remote handling techniques and technology from fusion re…
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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-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, …
Showing 21 - 30 of 79 UKAEA Paper Results