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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
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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
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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.
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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.
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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
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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
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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
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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
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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
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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
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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
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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
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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
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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
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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.
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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.
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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
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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
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