Results 31 to 40 of about 464 (186)

Initial design concepts for solid boron injection in ITER

open access: yesNuclear Materials and Energy
As part of ITER’s consideration to change its first wall material from beryllium to tungsten, the ITER Organization has proposed studying the feasibility of real-time solid boron injection (SBI) into the plasma to coat the walls and divertor to ...
J.A. Snipes   +14 more
doaj   +1 more source

A novel discontinuous-Galerkin deterministic neutronics model for fusion applications: workflow for stellarator reactor design studies

open access: yesNuclear Fusion
Stellarator reactor design and optimization requires quick and accurate neutronic simulations for obtaining tritium breeding ratio, coil neutron flux, and volumetric neutron heating.
Timo J. Bogaarts, Felix Warmer
doaj   +1 more source

Stellar activity [PDF]

open access: yesSymposium - International Astronomical Union, 1986
We have been monitoring the CaII H and K emission in late-type giant stars using the Mt Wilson 60-inch telescope. It is a continuation of work that Olin Wilson began almost 20 years ago. As a result not only have starspot cycles been detected (equivalent to the solar sunspot cycle), but rotation periods have now been measured.
openaire   +1 more source

Heat Load Mitigation Studies in the W7‐X Stellarator Experiment

open access: yesContributions to Plasma Physics, EarlyView.
ABSTRACT During the experiments at the stellarator Wendelstein 7‐X (W7‐X) with fully water‐cooled plasma‐facing components (PFC), including carbon‐fiber composite (CFC) divertor targets with a thermal load capability of 10 MW/m2, high performance was achieved.
Dirk Naujoks   +11 more
wiley   +1 more source

Implementation of the E×B and Grad‐B Drift in the EMC3 Code and Verification Using the Method of Manufactured Solutions

open access: yesContributions to Plasma Physics, EarlyView.
ABSTRACT Effective management of particle and power exhaust is essential for fusion reactor operation, requiring accurate 3D modeling of divertor physics. The EMC3 code is a well‐established Monte Carlo tool for plasma transport in stellarator edge regions, but until now lacked E×B$$ E\times B $$ and diamagnetic drifts.
Ruben De Wolf   +5 more
wiley   +1 more source

Effect of Magnetic Islands on Neoclassical Heat Diffusivity in a Global Tokamak Simulation

open access: yesContributions to Plasma Physics, EarlyView.
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

Impact of error fields and error field correction on heat fluxes in SPARC

open access: yesNuclear Fusion
Using a single toroidal array of coils to reduce the $m,n = 2,1$ resonant error field (EF) produced by the misalignment of the axisymmetric coils in SPARC can result in the enhancement of the local divertor heat fluxes. Managing high divertor heat fluxes
S. Munaretto   +6 more
doaj   +1 more source

Numerical studies on electron cyclotron resonance heating and optimization in the CN-H1 stellarator

open access: yesNuclear Engineering and Technology
The H1-NF stellarator in the Australian National University has been transported to University of South China and is currently being restored and reconstructed to the CN-H1 stellarator.
Chun Yan Li   +4 more
doaj   +1 more source

Towards a Mean‐Field Braginskii Model for Stellarators

open access: yesContributions to Plasma Physics, EarlyView.
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

Magneto‐Thermal Assessment of Ferrofluid Flow in Corrugated Porous Domain With Rotating Cylinder for Nuclear Systems

open access: yesInternational Journal of Energy Research, Volume 2026, Issue 1, 2026.
This research presents a novel approach by combining magnetohydrodynamic (MHD) flow with ohmic heating to investigate the conjugate mixed convective transport of ferrofluid in a discretely heated, smooth/wavy‐walled, square‐shaped porous compartment featuring a clockwise spinning cylindrical body positioned at various locations.
Nahid Hasan   +4 more
wiley   +1 more source

Home - About - Disclaimer - Privacy