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 …

Overview of the JET results in support to ITER

X Litaudon, S Abduallev, M Abhangi, P Abreu… - Nuclear …, 2017 - iopscience.iop.org
The European nuclear fusion research community has elaborated a Roadmap to the
realisation of fusion energy in which 'ITER is the key facility and its success is the most …

Integrated modeling of CFETR hybrid scenario plasmas

J Chen, VS Chan, X Jian, X Zhang, Q Ren, G Li… - Nuclear …, 2021 - iopscience.iop.org
Demonstration of DEMO relevant fusion power (Pfus) level and tritium self-sufficiency are
two important goals of the China fusion engineering testing reactor (CFETR). In this work the …

Recent Progress in Modeling of CFETR Plasma Profiles from Core to Edge

J Chen, G Jia, N Xiang - Journal of Fusion Energy, 2021 - Springer
Simulation studies of core plasmas and edge plasmas are performed in ASIPP to
accommodate plasma profiles from core to edge based on physics modeling for the CFETR …

Stability optimization of energetic particle driven modes in nuclear fusion devices: the FAR3d gyro-fluid code

J Varela, D Spong, L Garcia, Y Ghai, J Ortiz… - Frontiers in …, 2024 - frontiersin.org
The development of reduced models provide efficient methods that can be used to perform
short term experimental data analysis or narrow down the parametric range of more …

Subdominant modes and optimization trends of DIII-D reverse magnetic shear configurations

J Varela, DA Spong, M Murakami, L Garcia… - Nuclear …, 2019 - iopscience.iop.org
Alfvén Eigenmodes (AE) and magneto-hydrodynamic (MHD) modes are destabilized in DIII-
D reverse magnetic shear configurations and may limit the performance of the device. We …

Optimization of helicon wave off-axis current drive in CFETR tokamak

X Li, G Li, H Liu - Fusion Engineering and Design, 2021 - Elsevier
Abstract The China Fusion Engineering Testing Reactor (CFETR) is a tokamak reactor and
aims to eventually reach DEMO relevant fusion power level of 1 GW. A lower single null …

Turbulent transport analysis of JET H-mode and hybrid plasmas using QuaLiKiz and Trapped Gyro Landau Fluid

B Baiocchi, J Garcia, M Beurskens… - Plasma Physics and …, 2015 - iopscience.iop.org
The physical transport processes at the basis of JET typical inductive H-mode scenarios and
advanced hybrid regimes, with improved thermal confinement, are analyzed by means of …

Simulation of plasma scenarios for CFETR phase II based on engineering design parameters

YJ Zhong, QH Huang, XY Gong, QY Tan… - Fusion Engineering and …, 2021 - Elsevier
The China fusion engineering testing reactor (CFETR) is a proposed tokamak nuclear fusion
reactor in China, the purpose of which is to achieve large-scale power generation at the …

Core micro-instability analysis of JET hybrid and baseline discharges with carbon wall

S Moradi, I Pusztai, I Voitsekhovitch, L Garzotti… - Nuclear …, 2014 - iopscience.iop.org
The core micro-instability characteristics of hybrid and baseline plasmas in a selected set of
JET plasmas with carbon wall are investigated through local linear and non-linear and …