Results 291 to 300 of about 112,088 (330)
Some of the next articles are maybe not open access.

Partially detached radiative divertor with active divertor pumping

Nuclear Fusion, 1997
Deuterium fuelled radiative diverters, operating in the partially detached divertor (PDD) regime, are effective in reducing the heat load on the divertor target. These PDD discharges are shown to be compatible with active particle exhaust conditions-an important issue for ITER type operation.
T.W Petrie   +5 more
openaire   +1 more source

Kinetic Divertor Modeling [PDF]

open access: possible, 2011
The coupled dynamics and kinetics between gas and plasma in the divertor region is studied by means of a one-dimensional Particle in Cell-Direct Simulation Monte Carlo (PIC-DSMC) model. In particular, the collision-induced vibrational excitation/relaxation of H2 molecules and particle-surface interaction (vibrational relaxation and recombinative ...
Taccogna F, Minelli P, Bruno D
openaire   +2 more sources

Divertor Concepts II: The Dynamic Ergodic Divertor

Fusion Science and Technology, 2004
The Dynamic Ergodic Divertor (DED) has recently been taken into operation on the TEXTOR tokamak. One of the aims is the study of the mitigation of the heat flux by rotating the divertor strike points. After an introduction into the theory of ergodization, the design of the DED is presented.
openaire   +1 more source

Divertor for W7-X: II. Comparison of island and axisymmetric divertor

Plasma Physics and Controlled Fusion, 2002
The need for sufficient power and particle exhaust is common to all magnetic confinement concepts. For the new stellarator W7-X, making use of the intrinsic island structure at the edge, an island divertor is planned. The concept of the W7-X island divertor (as a prototype of general island divertors) and its specific design criteria will be presented.
Schneider, R.   +4 more
openaire   +2 more sources

Divertor plasma detachment

Physics of Plasmas, 2016
Regime with the plasma detached from the divertor targets (detached divertor regime) is a natural continuation of the high recycling conditions to higher density and stronger impurity radiation loss. Both the theoretical considerations and experimental data show clearly that the increase of the impurity radiation loss and volumetric plasma ...
S. I. Krasheninnikov   +2 more
openaire   +1 more source

Experimental divertor physics

Plasma Physics and Controlled Fusion, 1997
The physics of divertors in tokamaks is reviewed, primarily from an experimental point of view, although where possible simple analytic modelling is included. The paper covers the four main subject areas at issue in divertor research: (1) the wide dispersal of plasma power exhausted from the main plasma, (2) the production of sufficiently high gas ...
Pitcher, C., Stangeby, P.
openaire   +2 more sources

First Observation of a Stable Highly Dissipative Divertor Plasma Regime on the Wendelstein 7-X Stellarator.

Physical Review Letters, 2019
For the first time, the optimized stellarator Wendelstein 7-X has operated with an island divertor. An operation regime in hydrogen was found in which the total plasma radiation approached the absorbed heating power without noticeable loss of stored ...
D. Zhang   +41 more
semanticscholar   +1 more source

The ITER divertor

15th IEEE/NPSS Symposium. Fusion Engineering, 2002
The ITER divertor design is based on the high density exhaust concept of reducing peak heat fluxes falling on the divertor plates. The power is transferred from the edge plasma to the walls of the divertor chamber by atomic and molecular processes such as radiation, charge exchange, recombination, and gas conduction before it can reach tile divertor ...
K.J. Dietz, P.-H. Rebut
openaire   +2 more sources

PDX Divertor operation

Journal of Nuclear Materials, 1980
Abstract PDX was brought into operation in January 1980 as a diverted tokamak with typical parameters of B T = 15–20 kG, a = 38 cm, R 0 = 123–159 cm, I P = 180–300 kA, q ~ 3.7, n e = 1–3.8 × 10 13 cm −3 , Z = 1.1–3, t es ~ 25 ms , and pulse lengths up to 0.7s.
D.K Owens   +35 more
openaire   +1 more source

Advanced Divertor Concepts

Fusion Technology, 1996
LHD divertor development program has generated various innovative divertor concepts and technologies which will help to improve the plasma performance in both helical and tokamak devices. They are two divertor operational scenarios (confinement improvement by generating high temperature divertor plasma and simultaneous achievement of radiative cooling ...
N. Ohyabu   +8 more
openaire   +1 more source

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