Production of high transient heat and particle fluxes in a linear plasma device

Temmerman, G. De; Zielinski, JJ Jakub; Meiden, van der H.J.; Melissen, W; Rapp, J.

doi:10.1063/1.3484961

Cited by 25 publications

(26 citation statements)

References 11 publications

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“…Up to now, the heat load on the divertor in previous MCF systems has been unreached parameter. Thus, to predict properties of the divertor under these heat loads, several experiments have been performed using electron [5] or plasma guns [6,7], or intense laser intended to reproduce relevant heat fluxes [8]. These experiments have mainly been employed to evaluate metallurgical characteristics of the tungsten divertor.…”

Section: Introductionmentioning

confidence: 99%

Evaluation of Transport Properties in Warm Dense Matter Generated by Pulsed-power Discharge for Nuclear Fusion Systems

et al. 2015

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To achieve the thermonuclear fusion systems, the physical properties of warm dense matter (WDM) are key parameters. In this paper, we review the evaluation of physical properties in WDM by using pulsed-power discharges. To evaluate the thermal conductivity for a divertor wall in magnetic confinement fusion, we investigate a semi-empirical evaluation based on the experimental values for electrical resistivity. The results indicate that, in the region between the intermediate degeneracy and the non-degeneracy, the evaluated thermal conductivity has an inflection point. To evaluate the electrical resistivity for the fuel target in the inertial confinement fusion, an isochoric heating by using pulsed-power discharge in the pressure vessel has been demonstrated. The results indicate that the electrical resistivity in WDM for gold is 100 μΩ · m at 0.1ρ s (ρ s : solid density) of density and the internal energy is 1 MJ/kg.

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Section: Introductionmentioning

confidence: 99%

Evaluation of Transport Properties in Warm Dense Matter Generated by Pulsed-power Discharge for Nuclear Fusion Systems

et al. 2015

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“…The resulting steady state heat flux density of up to 40 MWm −2 perpendicular to the targets facilities reactor relevant heat flux tests. Moreover, a pulsed operation mode of the source is under development aiming at a transient power flux density of 2 GWm −2 for 0.5 ms to simulate transient loads [7]. Neutron damaged or toxic material cannot be handled but it is envisaged to simulate the impact of neutron activation by in situ high energy ion beam irradiation [4].…”

Section: Magnum-psimentioning

confidence: 99%

New linear plasma devices in the trilateral euregio cluster for an integrated approach to plasma surface interactions in fusion reactors

Unterberg¹,

Jaspers

Koch³

et al. 2011

Fusion Engineering and Design

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a b s t r a c tNew linear plasma devices are currently being constructed or planned in the Trilateral Euregio Cluster (TEC) to meet the challenges with respect to plasma surface interactions in DEMO and ITER: i) MAGNUM-PSI (FOM), a high particle and power flux device with super-conducting magnetic field coils which will reach ITER-like divertor conditions at high magnetic field, ii) the newly proposed linear plasma device JULE-PSI (FZJ), which will allow to expose toxic and neutron activated target samples to ITER-like fluences and ion energies including in vacuo analysis of neutron activated samples, and iii) the plasmatron VISION I, a compact plasma device which will be operated inside the tritium lab at SCK-CEN Mol, capable to investigate tritium plasmas and moderately activated wall materials. This contribution shows the capabilities of the new devices and their forerunner experiments (Pilot-PSI at FOM and PSI-2 Jülich at FZJ) in view of the main objectives of the new TEC program on plasma surface interactions.

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“…The continuous plasma can be combined with a transient heat and particle pulse (up to 1.2 GW Á m À2 for 1.2 ms), by superimposing a high current pulse onto the DC, allowing the study of ELM effects on plasma-exposed surfaces. 9,10 In the present work, the DC arc current was 200 A, while the pulse current was varied up to 10 kA. The typical evolution of the discharge current during a pulse is shown in Fig.…”

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confidence: 99%