Results 91 to 100 of about 36,485 (223)
A small steady-state tokamak capable of producing power in the 100 to 300 MWe range and relying on electron cyclotron RF heating (ECH) for both heating and current drive is described. Working in the first MHD stability regime for tokamaks, the approach adheres to the recently discovered maximum beta limit. An appropriate figure of merit is the ratio of
Firestone, M. A. +2 more
openaire +3 more sources
A Design Method of Divertor in Tokamak Reactors
"Computational method to design the efficient divertor configuration in tokamak reactor is presented. The two-dimensional code has been developed to analyze the distributions of the plasma and neutral particles for realistic configurations.
Itoh, K." +3 more
core
Helicon Wave Auxiliary Current Drive under D-T Plasma Operation Mode on HL-3 Tokamak Device
The D-T plasma discharge is a critical operational mode for reactor-grade Tokamak devices. The helicon wave current drive on HL-3 Tokamak device was studied in the paper.
WANG Sen1, ZI Daozheng1, CHENG Zehou1, LI Xinxia1, 2,
doaj +1 more source
Completely bootstrapped tokamak
A fundamental requirement for the successful operation of a tokamak is the maintenance of a toroidal electric current within the tokamak plasma itself. Maintaining this internal plasma current can be a very difficult technological problem.
Weening, Richard Henry
core +1 more source
Tritium production and processing systems for ST-E1
An integrated tritium fuel-cycle architecture has been developed for ST-E1, a low-aspect-ratio, high-power fusion power plant. The approach couples a helium-cooled liquid-lithium breeder blanket with a dedicated circulation loop providing tritium ...
E. Yildirim +19 more
doaj +1 more source
Numerical Studies and Simulation of the Lower Hybrid Waves Current Drive by using Fokker – Planck Equation in NSST and HT-7 Tokamaks [PDF]
Recent experiments on the spherical tokamak have discovered the conditions to create a powerful plasma and ensure easy shaping and amplification of stability, high bootstrap current and confinement energy.
A.A. Molavi Choobini
doaj
Implementation of an Iter-relevant Qp-based Current Limit Avoidance Algorithm in the Tcv Tokamak
The problem of avoiding saturation of the coil currents is critical in large tokamaks with superconducting coils like ITER. Indeed, if the current limits are reached, a loss of control of the plasma may lead to a major disruption.
Pironti, Alfredo +11 more
core +1 more source
V-band nanosecond-scale pulse reflectometer diagnostic in the TCV tokamak [PDF]
This article describes the realization of a novel approach to short pulse (∼1 ns) reflectometry (SPR) recently implemented in the tokamak configuration variable tokamak.
Smolders, A. +3 more
core +1 more source
Numerical Simulation of Internal Reconnection Event in Spherical Tokamak
"Three dimensional magnetohydrodynamic simulations are executed in a full toroidal geomety to clarify the physical mechanisms of the Internal Reconnection Event (IRE), which is observed in the spherical tokamak experiments.
Mizuguchi, N. +3 more
core
The complexity and significance of multiscale phenomena in fusion energy systems make advanced modeling necessary for designing, optimizing, and safely deploying fusion plants.
Lin Yang +5 more
doaj +1 more source

