Results 81 to 90 of about 12,708 (208)
Toward plasma drifts in EMC3: Implementation of gradient, divergence, and particle tracing schemes
Abstract This paper presents a first implementation of gradient, divergence, and particle tracing schemes for the EMC3 code, a stochastic 3D plasma fluid code widely employed for edge plasma and impurity transport modeling in tokamaks and stellarators.
Ruben De Wolf +6 more
wiley +1 more source
Electron cyclotron wall conditioning with argon gas (Ar-ECWC) has been performed on the normal conducting spherical tokamak QUEST with metal walls for the purpose of applying this technique to future superconducting fusion devices with metal walls as an ...
Masakatsu Fukumoto +22 more
doaj +1 more source
Calculation of in-situ steady-state heat flux on EAST lower divertor
Heat flux is a key issue in tokamak devices. The non-uniform high heat flux on Plasma-Facing Components (PFCs) has led to local severe damage, including cracks and melting, in current tokamaks such as EAST and WEST.
Chunyu He +12 more
doaj +1 more source
Microturbulence studies in RFX-mod
Present-days Reversed Field Pinches (RFPs) are characterized by quasi-laminar magnetic configurations in their core, whose boundaries feature sharp internal transport barriers, in analogy with tokamaks and stellarators.
Bonfiglio D +17 more
core +1 more source
STABLE REGION OF TOKAMAK DEVICE FEEDBACK CONTROL (Ⅱ)——EXPBEIMENTAL
A stable region experiment of feedback control in CT-6B Tokamak has been can-ducted. Two feedback systems have been used simultaneously to control the heating field and the vertical magnetic field in the Tokamak. The experimental results were compared with the linear theory described in the part (I) of our paper.
null Shen Zhong-qing +2 more
openaire +1 more source
Testing of the SOLPS-ITER code at Globus-M2 spherical tokamak with detached divertor
In according to a present understanding of Scrape-Off Layer (SOL) physics, future thermonuclear devices like ITER, DEMO and beyond, require high radiation regimes in order to reduce heat loads on tokamak divertor. Recent experiments at ASDEX Upgrade, JET
Sorokina Daria +3 more
doaj +1 more source
Tokamak divertor plasma emulation with machine learning
Future tokamak devices that aim to create conditions relevant to power plant operations must consider strategies for mitigating damage to plasma facing components in the divertor.
G.K. Holt +7 more
doaj +1 more source
Error field detection and correction studies towards ITER operation
In magnetic fusion devices, error field (EF) sources, spurious magnetic field perturbations, need to be identified and corrected for safe and stable (disruption-free) tokamak operation.
L. Piron +37 more
doaj +1 more source
STABLE REGION OF TOKAMAK DEVICE FEEDBACK CONTROL (Ⅰ)——THEORETICAL
In this paper, the evolution equations of feedback control of plasma current and horizontal displacement simultineously in a tokamak device are presented. Under the assumption of small disturbance and linear approximation, the stability criterion and the stable region of CT-6B tokamak feedback control is given.
null ZHENG SHAO-BAI +1 more
openaire +1 more source
Based on the analysis of a large number of high-fidelity nonlinear gyrokinetic simulations, we propose a novel strategy to improve confinement in spherical tokamak plasmas by combining up-down asymmetric flux surface shaping with the Low Momentum ...
Haomin Sun +10 more
doaj +1 more source

