Metis: a fast integrated tokamak modelling tool for scenario design

JF Artaud, F Imbeaux, J Garcia, G Giruzzi, T Aniel… - Nuclear …, 2018 - iopscience.iop.org
METIS is a numerical code aiming at fast full tokamak plasma analyses and predictions. It
combines 0D scaling-law normalised heat and particle transport with 1D current diffusion …

ITER breakdown and plasma initiation revisited

PC De Vries, Y Gribov - Nuclear Fusion, 2019 - iopscience.iop.org
This paper revisits a number of key aspects of plasma initiation, aiming to clarify concepts,
provide definitions and improve understanding, in view of ITER First Plasma operation. It …

ITER plasma control system final design and preparation for first plasma

JA Snipes, PC De Vries, Y Gribov… - Nuclear …, 2021 - iopscience.iop.org
The ITER plasma control system (PCS) has successfully completed its final design for the
first plasma (FP) and engineering operations (EOs) phase and plant system commissioning …

Investigation of key parameters for the development of reliable ITER baseline operation scenarios using CORSICA

SH Kim, TA Casper, JA Snipes - Nuclear Fusion, 2018 - iopscience.iop.org
ITER will demonstrate the feasibility of burning plasma operation by operating DT plasmas
in the ELMy H-mode regime with a high ratio of fusion power gain Q~ 10. 15 MA ITER …

Multi-machine analysis of termination scenarios with comparison to simulations of controlled shutdown of ITER discharges

PC de Vries, TC Luce, YS Bae, S Gerhardt… - Nuclear …, 2017 - iopscience.iop.org
To improve our understanding of the dynamics and control of ITER terminations, a study has
been carried out on data from existing tokamaks. The aim of this joint analysis is to compare …

The ITER disruption mitigation trigger: developing its preliminary design

G Pautasso, PC De Vries, D Humphreys… - Nuclear …, 2018 - iopscience.iop.org
A concept for the generation of the trigger for the ITER disruption mitigation system is
described in this paper. The issuing of the trigger will be the result of a complex decision …

Evaluation of fuelling requirements for core density and divertor heat load control in non-stationary phases of the ITER DT 15 MA baseline scenario

F Koechl, R Ambrosino, P Belo, M Cavinato… - Nuclear …, 2020 - iopscience.iop.org
To ensure optimal plasma performance at high Q fus for the baseline scenario foreseen for
ITER, the fuelling requirements, in particular for non-stationary phases, need to be assessed …

Summary of the FESAC transformative enabling capabilities panel report

R Maingi, A Lumsdaine, JP Allain… - Fusion Science and …, 2019 - Taylor & Francis
Abstract The US Fusion Energy Sciences Advisory Committee was charged “to identify the
most promising transformative enabling capabilities (TEC) for the US to pursue that could …

Stabilizing elongated plasmas using extremum seeking: the ITER tokamak case study

G De Tommasi, S Dubbioso, A Mele… - … Conference on Control …, 2021 - ieeexplore.ieee.org
In this paper we propose a model-free approach to stabilize vertical unstable plasmas in
tokamak devices. The approach relies on the extremum seeking algorithm and on averaging …

Development of synthetic diagnostics for ITER First Plasma operation

J Sinha, PC De Vries, L Zabeo… - Plasma Physics and …, 2021 - iopscience.iop.org
Abstract ITER First Plasma (FP) operation aims to produce a plasma with current higher than
100 kA for a duration longer than 100 ms. However, the low values of plasma density and …