Results 301 to 310 of about 112,088 (330)
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TCV heating and divertor upgrades

Nuclear Fusion, 2019
The operational range and the reactor relevance of the TCV experiments are being enhanced by two sets of major upgrades. The first includes the installation of neutral beam injection (NBI) and new electron cyclotron (EC) auxiliary heating sources, to ...
A. Fasoli   +12 more
semanticscholar   +1 more source

Divertor detachment and asymmetry in H-mode operation with an ITER-like tungsten divertor in EAST

Nuclear Fusion, 2019
The detached divertor has recently been achieved in H-mode plasmas in EAST with an ITER-like tungsten divertor, which is essential for high power long pulse operation in the near future.
J. Liu   +22 more
semanticscholar   +1 more source

DEMO divertor maintenance

Fusion Engineering and Design, 2009
Abstract This paper presents a DEMO divertor segmentation and maintenance scheme together with maintenance time estimations. As far as it is known, it is the first such study for DEMO, and the work was coordinated by EFDA. The approach of the study was that DEMO divertor and its handling shall be very similar to that of ITER, therefore ITER divertor ...
D. Nagy   +3 more
openaire   +1 more source

TPX divertor design

15th IEEE/NPSS Symposium. Fusion Engineering, 2002
The TPX tokamak incorporates a double null slot divertor that may be operated in a single or double null mode. Provisions are incorporated to provide for radiative divertor operation to reduce the peak heat flux to the divertor. Particle pumping is provided through vertical ports to control the plasma density. This paper describes the conceptual design
P.M. Anderson   +6 more
openaire   +1 more source

Poloidal divertor experiment

Physics Today, 1976
Construction has begun on the Poloidal Divertor Experiment at Princeton University's Plasma Physics Laboratory. The $18-million device, expected to begin operation by December 1977, will be used to test the effectiveness of poloidal field divertors and magnetic limiters to control impurities in tokamaks.
openaire   +1 more source

Divertor Tokamak Experiments

1986
A future tokamak reactor has to fulfill several requirements: good confinement properties to achieve ignition at low external heating power; high stability at minimal toroidal magnetic field strength; and efficient helium removal from the system for continuous burn.
Wagner, F.   +3 more
openaire   +3 more sources

Divertor closure effects on the TCV boundary plasma

Nuclear Materials and Energy, 2021
Olivier FĂ©vrier   +2 more
exaly  

Divertor Component Testing

2022
Travis Gray   +3 more
openaire   +1 more source

Surface heat loads on the ITER divertor vertical targets

, 2017
J. P. Gunn   +15 more
semanticscholar   +1 more source

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