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UKAEA-CCFE-PR(25)3792025
A robust disruption mitigation system (DMS) requires accurate characterization of key disruption timescales, one of the most notable being the thermal quench (TQ). Recent modeling of shattered pellet injection (SPI) into ITER plasmas, using JOREK and INDEX, suggests long TQ durations (6–10 ms) and slow cold front propagation due to the large p…
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UKAEA-CCFE-PR(25)3672025
This study presents the validation of the finite element code ERMES 20.0, benchmarked against the well-established method-of-moments code TOPICA. The simulations focus on Ion Cyclotron Resonance Heating (ICRH) coupling for the JET A2 antennas. Validation is performed by comparing two key metrics: the scattering parameter matrix (S-matrix) and the …
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UKAEA-CCFE-PR(25)3552025
This study presents results from particle transport modelling for D/T ratio control experiments conducted during the JET DTE3 campaign. TRANSP interpretative and JETTO predictive simulations for D and T densities were performed and their results are discussed. Despite using simplified models based on Bohm-gyroBohm transport, the simulations inco…
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UKAEA-CCFE-PR(25)3462025
The JET Restart process is a critical phase in the operation of the Joint European Torus (JET), enabling the transition of JET plant from Shutdown to experimental plasma campaigns. This paper provides a comprehensive overview divided into its two main stages. The first stage, Integrated Commissioning, encompasses the activation and synchronizatio…
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UKAEA-CCFE-PR(25)3412025
Predictions of the pedestal temperature profile calculated using a model for ETG turbulent electron heat transport [A R Field et al 2023 Phil. Trans. Royal Soc. A 381 (2242) 20210228] are compared with the pedestal structure of JET-ILW (‘ITER-like wall’) H-mode plasmas over scans of the deuterium-tritium (D:T) isotope mix and hydrogenic gas fue…
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UKAEA-CCFE-PR(25)3392025
Fusion performance in a tokamak-reactor strongly depends on the confinement of thermalised α-particles (Helium (He) ash) in the core plasma region. Consequently, the development of He particle transport models and their validation in present experiments is an important step towards a more accurate prediction of fusion power production in future de…
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UKAEA-RACE-PR(25)052025
This paper presents a technical overview of AutoInspect, a ROS-based software system for robust and extensible mission-level autonomy. Over the past three years we have deployed AutoInspect on multiple platforms in a variety of environments, from forests to fusion reactors, for durations ranging from hours to weeks. The AutoInspect system combin…
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UKAEA-CCFE-PR(25)3352025
The calibration of the JET x-ray spectrometer is presented. The absolute throughput, diffractor focussing and instrument function of the spectrometer is presented and the quality of the ion temperature measurement is re-assessed, particularly at the lower end. The addition of a second diffractor enables simultaneous measurements of the spectra …
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UKAEA-CCFE-PR(25)3152025
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 Deuterium-Tritium 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(25)3102025
An optical interlock protects the JET neutral beam ducts from damage if there is a fast pressure rise in the beam duct. The ability to trip during fault conditions and avoidance of false trips is limited by background light from the plasma and the additional light from radiation effects. A false trip occurred during the JET-DTE2 experimental cam…
Showing 11 - 20 of 510 UKAEA Paper Results