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 …

In a series of high performance diverted discharges on DIII-D, we demonstrate that strong
negative triangularity (NT) shaping robustly suppresses all edge-localized mode (ELM) …

Fusion whole device modeling simulations require comprehensive models that are
simultaneously physically accurate, fast, robust, and predictive. In this paper we describe the …

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 …

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 …

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 …

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 …

Instability to high toroidal mode number (n) ballooning modes has been proposed as the
primary gradient-limiting mechanism for tokamak equilibria with negative triangularity …

Diverted discharges at negative triangularity on the DIII-D tokamak sustain normalized
confinement and pressure levels typical of standard H-mode scenarios (H 98y2≃ 1, β N≃ 3) …

Recent progress in the application of machine learning (ML)/artificial intelligence (AI)
algorithms to improve the Equilibrium Fitting (EFIT) code equilibrium reconstruction for …