Results 31 to 40 of about 37,750 (180)
Tungsten boride shields in a spherical tokamak fusion power plant [PDF]
The favourable properties of tungsten borides for shielding the central high temperature superconductor (HTS) core of a spherical tokamak fusion power plant are modelled using the MCNP code.
Davidson, James J +13 more
core +1 more source
Effect of Magnetic Islands on Neoclassical Heat Diffusivity in a Global Tokamak Simulation
ABSTRACT Resonant magnetic perturbations (RMPs) alter magnetic field topology via island formation and can modify core transport in toroidal fusion devices. Using the global gyrokinetic particle‐in‐cell code XGC‐S, originally developed for stellarator geometries, we quantify how island topology affects neoclassical heat transport in a circular tokamak ...
Joseph X. Li +5 more
wiley +1 more source
Tokamak Energy’s pre-concept design for a fusion power plant: an overview of ST-E1
Climate change and rapidly rising energy demand, driven in part by artificial intelligence and data-centre growth, create an urgent need for stable, low-carbon, and abundant power. Fusion is a promising long-term solution, yet its commercialisation faces
J. Willis +84 more
doaj +1 more source
This paper describes a family of relatively simple numerical models for calculation of asymmetric electromagnetic (EM) loads at all tokamak structures and coils at asymmetric vertical plasma displacement events (AVDE). Unlike currently known AVDE studies
Sergey Sadakov +3 more
doaj +1 more source
Plasma boundary reconstruction and shape control of Tokamak discharges in RFX-mod [PDF]
La tesi si occupa del controllo di forma del plasma in configurazione Tokamak a doppio nullo nell’esperimento RFX-mod. Vengono affrontate problematiche di ricostruzione della forma, con un apporto originale nell’utilizzo di una interpolante thin plate ...
Merlo, Pierangelo
core
First SOLPS‐ITER Simulation Study of Japanese DEMO on Leakage of Seeded Ar Impurity
ABSTRACT For JA DEMO, one of the grand challenges is efficiently handling the extreme power loads onto plasma‐facing components, particularly the divertor targets. Impurity seeding is an essential strategy for increasing the radiation losses and thereby reducing the heat load on the targets.
Hang Si +6 more
wiley +1 more source
Inferring the scrape-off layer heat flux width in a divertor with a low degree of axisymmetry
Plasma facing components (PFCs) in the next generation of tokamak devices will operate in challenging environments, with heat loads predicted to exceed 10 MW/m2. The magnitude of these heat loads is set by the width of the channel, the ‘scrape-off layer’
C. Marsden +8 more
doaj +1 more source
Numerical tokamak turbulence project (OFES grand challenge) [PDF]
The primary research objective of the Numerical Tokamak Turbulence Project (NTTP) is to develop a predictive ability in modeling turbulent transport due to drift-type instabilities in the core of tokamak fusion experiments, through the use of three ...
Nevins, W. M. +18 more
core +1 more source
Towards a Mean‐Field Braginskii Model for Stellarators
ABSTRACT Experiments in the stellarator Wendelstein 7‐X indicate that particle drifts have a significant impact on the plasma in the scrape‐off layer. However, drift effects have been absent in the mean‐field transport codes such as EMC3‐Eirene. For this reason, we present the first steps towards a mean‐field model that incorporates drifts. The code is
T. Tork +7 more
wiley +1 more source
Thermal management and net-power evaluation of the ST-E1 fusion power plant
A comprehensive analysis of the thermal management and net-power performance is presented for the ST-E1 low aspect ratio tokamak fusion power plant. The study addresses the critical interplay between coolant system design, power cycle integration, and ...
Mohamed Khalid Elsharif Mohamed +12 more
doaj +1 more source

