ICRH analysis of high-performance JET hybrid discharges using PION modelling and neutron spectrometry measurements

The hybrid scenario is an operational tokamak plasma regime designed to achieve long pulse operat ion with a combination of inductive and non-inductive current drive. It has been suggested for ITER to allow operation at a high fusion power over 1000 s at a lower plasma currentthan for the inductive reference scenario. In the recent 2014 JET experimental campaign with the new ITER-like-wall (ILW) and deuterium as the main gas, high-performance hybrid discharges have been achieved with combined deuterium neutral beam injection (NBI) and ion cyclotron resonance heating (ICRH).This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 2014-2018 under grant agreement No 33053. The views and opinions expressed herein do not necessarily reflect those of the European Commission.Peer ReviewedPostprint (published version

Untersuchung zur Lernkultur in Online-Kursen

Ausgehend von einer veränderten, durch Lern- und Kompetenzorientierung geprägten Lernkultur analysieren die Autorinnen zwölf mehrwöchige Online-Kurse mit insgesamt 130 Teilnehmer/innen. Die Autorinnen nehmen ein Klima der hohen Wertschätzung unter den Lernenden wahr sowie gegenseitiges Feedback in den Reflexions- und Diskussionsprozessen, welches das Lernen verstärkt. Die Hypothese, dass in rein virtuellen, mehrwöchigen Weiterbildungskursen eine veränderte Lernkultur gefördert und gelebt wird, wird mittels halbstrukturierter Interviews sowie qualitativer Inhaltsanalyse der Beiträge in den Diskussionsforen untersucht. (DIPF/ Orig.

Mise au point d'une analyse multi-résidus de produits phytosanitaires dans les miels, les abeilles et le pollen par LC-MS/MS et GC-ToF

communication par afficheNational audienc

Development of multi-residue routine analysis of 80 pesticides in honeys, honeybees and pollens

International audienc

Versatile fusion source integrator AFSI for fast ion and neutron studies in fusion devices

ASCOT Fusion Source Integrator AFSI, an efficient tool for calculating fusion reaction rates and characterizing the fusion products, based on arbitrary reactant distributions, has been developed and is reported in this paper. Calculation of reactor-relevant D-D, D-T and D-(3) He fusion reactions has been implemented based on the Bosch-Hale fusion cross sections. The reactions can be calculated between arbitrary particle populations, including Maxwellian thermal particles and minority energetic particles. Reaction rate profiles, energy spectra and full 4D phase space distributions can be calculated for the non-isotropic reaction products. The code is especially suitable for integrated modelling in self-consistent plasma physics simulations as well as in the Serpent neutronics calculation chain. Validation of the model has been performed for neutron measurements at the JET tokamak and the code has been applied to predictive simulations in ITER

SOLPS-ITER drift modelling of JET Ne and N-seeded H-modes

A numerical study is presented, using the SOLPS-ITER plasma boundary code with full drifts and currents activated, of impurity seeded JET discharges in support of high power H-mode experimental campaigns designed to compare two ITER candidate seeding species, nitrogen (N) and neon (Ne). Fluid-kinetic edge plasma simulations are first performed at lower levels of power into the scrape-off layer (SOL) and benchmarked against existing JET experimental data. Calculations are then performed for higher levels of SOL power to examine the impact of this key parameter on the efficiency of both radiators. From the code point of view, for the chosen JET parameters, Ne can be as efficient a divertor radiator as N at the same level of upstream separatrix Zeff < 1.5 for moderate seeding, decreasing the peak power at outer target by factor ~ 3. Full detachment (state with the temperature below 5 eV along all the target) at the outer target can be obtained with both impurities at higher seeding, but in the case of Ne this leads to a higher Zeff and significant radiation in the main SOL/pedestal. The indications from this JET code modelling, in comparison with previous similar simulations for ITER and ASDEX Upgrade with drifts turned on, are that there is a beneficial impact of machine size in improving impurity retention, substantiating the claim that both N and Ne will perform well as seed impurities for divertor power dissipation in ITER

Recent progress in the quantitative validation of JOREK simulations of ELMs in JET

Future devices like JT-60SA, ITER and DEMO require quantitative predictions of pedestal density and temperature levels, as well as inter-ELM and ELM divertor heat fluxes, in order to improve global confinement capabilities while preventing divertor erosion/melting in the planning of future experiments. Such predictions can be obtained from dedicated pedestal models like EPED, and from non-linear MHD codes like JOREK, for which systematic validation against current experiments is necessary. In this paper, we show progress in the quantitative validation of the JOREK code using JET simulations. Results analyse the impact of diamagnetic terms on the dynamics and size of the ELMs, and evidence is provided that the onset of type-I ELMs is not governed by linear MHD stability alone, but that a nonlinear threshold could be responsible for large MHD events at the plasma edge.Peer ReviewedPostprint (published version

ICRH analysis of high-performance JET hybrid discharges using PION modelling and neutron spectrometry measurements

The hybrid scenario is an operational tokamak plasma regime designed to achieve long pulse operat ion with a combination of inductive and non-inductive current drive. It has been suggested for ITER to allow operation at a high fusion power over 1000 s at a lower plasma currentthan for the inductive reference scenario. In the recent 2014 JET experimental campaign with the new ITER-like-wall (ILW) and deuterium as the main gas, high-performance hybrid discharges have been achieved with combined deuterium neutral beam injection (NBI) and ion cyclotron resonance heating (ICRH).This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 2014-2018 under grant agreement No 33053. The views and opinions expressed herein do not necessarily reflect those of the European Commission.Peer Reviewe