Progress of the CFETR design
G Zhuang, GQ Li, J Li, YX Wan, Y Liu, XL Wang… - Nuclear …, 2019 - iopscience.iop.org
Abstract The Chinese Fusion Engineering Testing Reactor (CFETR), complementing the
ITER facility, is aiming to demonstrate fusion energy production up to 200 MW initially and to …
ITER facility, is aiming to demonstrate fusion energy production up to 200 MW initially and to …
Robust avoidance of edge-localized modes alongside gradient formation in the negative triangularity tokamak edge
In a series of high performance diverted discharges on DIII-D, we demonstrate that strong
negative triangularity (NT) sha** robustly suppresses all edge-localized mode (ELM) …
negative triangularity (NT) sha** robustly suppresses all edge-localized mode (ELM) …
Self-consistent core-pedestal transport simulations with neural network accelerated models
Fusion whole device modeling simulations require comprehensive models that are
simultaneously physically accurate, fast, robust, and predictive. In this paper we describe the …
simultaneously physically accurate, fast, robust, and predictive. In this paper we describe the …
NSTX-U research advancing the physics of spherical tokamaks
JW Berkery, PO Adebayo-Ige, H Al Khawaldeh… - Nuclear …, 2024 - iopscience.iop.org
The objectives of NSTX-U research are to reinforce the advantages of STs while addressing
the challenges. To extend confinement physics of low-A, high beta plasmas to lower …
the challenges. To extend confinement physics of low-A, high beta plasmas to lower …
A real-time machine learning-based disruption predictor in DIII-D
C Rea, KJ Montes, KG Erickson, RS Granetz… - Nuclear …, 2019 - iopscience.iop.org
A disruption prediction algorithm, called disruption prediction using random forests (DPRF),
has run in real-time in the DIII-D plasma control system (PCS) for more than 900 discharges …
has run in real-time in the DIII-D plasma control system (PCS) for more than 900 discharges …
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 …
Predictions of core plasma performance for the SPARC tokamak
SPARC is designed to be a high-field, medium-size tokamak aimed at achieving net energy
gain with ion cyclotron range-of-frequencies (ICRF) as its primary auxiliary heating …
gain with ion cyclotron range-of-frequencies (ICRF) as its primary auxiliary heating …
Simultaneous access to high normalized density, current, pressure, and confinement in strongly-shaped diverted negative triangularity plasmas
Strongly-shaped diverted negative triangularity (NT) plasmas in the DIII-D tokamak
demonstrate simultaneous access to high normalized density, current, pressure, and …
demonstrate simultaneous access to high normalized density, current, pressure, and …
Machine learning for disruption warnings on Alcator C-Mod, DIII-D, and EAST
This paper reports on disruption prediction using a shallow machine learning method known
as a random forest, trained on large databases containing only plasma parameters that are …
as a random forest, trained on large databases containing only plasma parameters that are …
Prospects for H-mode inhibition in negative triangularity tokamak reactor plasmas
Instability to high toroidal mode number (n) ballooning modes has been proposed as the
primary gradient-limiting mechanism for tokamak equilibria with negative triangularity …
primary gradient-limiting mechanism for tokamak equilibria with negative triangularity …