Overview of interpretive modelling of fusion performance in JET DTE2 discharges with TRANSP
Ž Štancar, KK Kirov, F Auriemma, HT Kim… - Nuclear …, 2023 - iopscience.iop.org
In the paper we present an overview of interpretive modelling of a database of JET-ILW
2021 DT discharges using the TRANSP code. The main aim is to assess our capability of …
2021 DT discharges using the TRANSP code. The main aim is to assess our capability of …
Radiation induced non-linear oscillations in ITER Baseline scenario plasmas in DIII-D
This work shows how the radiation brought about by metals or metal-equivalent radiators
such as Kr and Xe produces non-linear dynamics on otherwise stationary β N flattops of DIII …
such as Kr and Xe produces non-linear dynamics on otherwise stationary β N flattops of DIII …
Line identification of extreme ultraviolet (EUV) spectra from iron, copper and molybdenum ions in EAST tokamak
W Zhang, L Zhang, Y Cheng, S Morita, Z Wang… - Physica …, 2022 - iopscience.iop.org
Extreme ultraviolet (EUV) spectra emitted from iron and copper ions in a range of 8–500 Å
and molybdenum ions in a range of 8–400 Å were measured in Experimental Advanced …
and molybdenum ions in a range of 8–400 Å were measured in Experimental Advanced …
Full-radius integrated modelling of ASDEX Upgrade L-modes including impurity transport and radiation
D Fajardo, C Angioni, R Dux, E Fable, U Plank… - Nuclear …, 2024 - iopscience.iop.org
An integrated framework that demonstrates multi-species, multi-channel modelling
capabilities for the prediction of impurity density profiles and their feedback on the main …
capabilities for the prediction of impurity density profiles and their feedback on the main …
Scenario optimization for the tokamak ramp-down phase in RAPTOR. Part B: safe termination of DEMO plasmas
S Van Mulders, O Sauter, C Contré… - Plasma Physics and …, 2023 - iopscience.iop.org
An optimized plasma current ramp-down strategy is critical for safe and fast termination of
plasma discharges in a tokamak demonstration fusion reactor (DEMO), both in planned and …
plasma discharges in a tokamak demonstration fusion reactor (DEMO), both in planned and …
Turbulent transport driven by kinetic ballooning modes in the inner core of JET hybrid H-modes
Turbulent transport in the inner core of the high-β JET hybrid discharge 75225 is
investigated extensively through linear and non-linear gyro-kinetic (GK) simulations using …
investigated extensively through linear and non-linear gyro-kinetic (GK) simulations using …
Understanding core heavy impurity transport in a hybrid discharge on EAST
The behavior of heavy/high-Z impurity tungsten (W) in the core of hybrid (high normalized
beta β N plasmas) scenario on EAST with international thermonuclear experimental reactor …
beta β N plasmas) scenario on EAST with international thermonuclear experimental reactor …
Integrated modelling of tungsten accumulation control with wave heating: validation in ASDEX Upgrade and predictions for ITER
In present-day fusion devices, central wave heating is crucial to avoid core tungsten (W)
accumulation. In this work, we present an integrated modelling framework that reproduces …
accumulation. In this work, we present an integrated modelling framework that reproduces …
[PDF][PDF] Termination of discharges in high performance scenarios in JET
• The termination of high performance plasmas in tokamak devices with high Z metal plasma
facing components presents challenges related to the influx of heavy impurities which, if not …
facing components presents challenges related to the influx of heavy impurities which, if not …
A study of the heating and current drive options and confinement requirements to access steady-state plasmas at Q∼ 5 in ITER and associated operational scenario …
Access to steady-state (SS) plasma scenarios that can be potentially achieved in ITER by
the exploitation of the neutral beam (NB) and electron cyclotron (EC) heating and current …
the exploitation of the neutral beam (NB) and electron cyclotron (EC) heating and current …