Divertor conditions relevant for fusion reactors achieved with linear plasma generator

Eck, H.J.N. van; Kleyn, A.W.; Lof, Andries; Meiden, H.J. van der; Rooij, G.J. van; Scholten, J.; Emmichoven, P.A. Zeijlmans van

doi:10.1063/1.4768302

Cited by 23 publications

(20 citation statements)

References 19 publications

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“…Additionally, seeding gases (H2, D2, He, N2, Ne, Ar…) can now be introduced to this third chamber to adjust the neutral background pressure and composition at will, enabling detachment and seeding experiments [6]. By using this differential pumping scheme, the neutral pressure in the target region is low enough that the dominant source of neutrals in the final chamber is dominated by recycling from the target [7] and the plasma beam is transported from the source to the target with minimal losses. The magnetic field is generated by a superconducting magnet consisting of five NbTi superconducting solenoids wound on a 2.5 m long stainless steel coil former positioned in a cryostat offering a 1.25 m warm bore [8].…”

Section: Methodsmentioning

confidence: 99%

High-fluence and high-flux performance characteristics of the superconducting Magnum-PSI linear plasma facility

Eck

Akkermans

Westen

et al. 2019

Fusion Engineering and Design

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The Magnum-PSI facility is available for plasma-material interaction studies. • Magnum-PSI is capable to reach relevant plasma parameters for the ITER divertor. • Particle fluxes over 10 25 m-2 s-1 and heat fluxes of up to 50 MWm-2 are obtained. • Particle fluences of up to 10 30 particles m-2 have been achieved. • Linear regression and artificial neural network analysis have been applied.

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Section: Methodsmentioning

confidence: 99%

High-fluence and high-flux performance characteristics of the superconducting Magnum-PSI linear plasma facility

Eck

Akkermans

Westen

et al. 2019

Fusion Engineering and Design

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“…The plasma source was operated using a DC current of 150-190 A and H gas flow in the range 5.0-7.0 Pa m 3 s −1 . By switching on the axial magnetic field (up to 1.9 T [14]) the plasma was confined into a beam hitting the target (biased to -38 V) resulting in a particle flux of 1.5-3x10 23 m −2 s −1 , electron temperature 1-2 eV and a heat flux density in this case up to ∼2.5 MW m −2 in the centre of the plasma column. Transient heating was performed using a 1064 nm high power fibre-coupled Nd:YAG laser (LASAG FLS 352-302) with a pulse duration of 1 ± 0.1 ms, 10-25 Hz repetition rate and 1-21 kW input power.…”

Section: Setupmentioning

confidence: 99%

The effect of high-flux H plasma exposure with simultaneous transient heat loads on tungsten surface damage and power handling

Eden¹,

Morgan²,

Meiden³

et al. 2014

Nucl. Fusion

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The performance of the full-W ITER divertor may be significantly affected by the interplay between steady-state plasma exposure and transient events. To address this issue, the effect of a high-flux H plasma on the thermal shock response of W to ELM-like transients has been investigated. Transient heating of W targets is performed by means of a high-power Nd:YAG laser with simultaneous exposure to H plasma in the linear device Magnum-PSI. The effects of simultaneous exposure to laser and plasma has been compared to those sequentially and to laser only. Transient melting is found to be aggravated during plasma exposure and to occur at lower heat flux parameters. Roughness and grain growth are observed to be driven by peak temperature, rather than by the loading conditions. The temperature evolution of the W surface under a series of transients is recorded by fast infrared thermography. By accounting for changes in the reflectivity at the damaged surface as measured by ellipsometry, a reduction in power handling capabilities of the laser/plasma affected W is concluded. The evidence of reduced power handling of the W surface under conditions as described here is of great concern with respect to the durability of W PFCs for application in fusion devices.

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“…The advanced linear plasma generators Magnum-PSI 5,6 and Pilot-PSI 7,8 have the ability to produce ITER-relevant divertor plasma conditions with high density (electron density >4 Â 10 21 m…”

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confidence: 99%

Collective Thomson scattering system for determination of ion properties in a high flux plasma beam

Meiden

Vernimmen

Bystrov

et al. 2016

Applied Physics Letters

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A collective Thomson scattering system has been developed for measuring ion temperature, plasma velocity and impurity concentration in the high density magnetized Magnum-PSI plasma beam, allowing for measurements at low temperature (<5 eV) and high electron density >4 × 1020 m−3, while avoiding laser plasma heating caused by inverse Bremsstrahlung. The collective Thomson scattering system is based on the fundamental mode of a seeded Nd:YAG laser and equipped with an LIVAR M506 camera (EBABS technology). The first collective Thomson scattering measurements are taken at the linear plasma generator Pilot-PSI, 40 mm downstream of the cascaded arc source. At this location, the ion temperature is about equal to the electron temperature in the bulk of the plasma beam.

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Divertor conditions relevant for fusion reactors achieved with linear plasma generator

Cited by 23 publications

References 19 publications

High-fluence and high-flux performance characteristics of the superconducting Magnum-PSI linear plasma facility

High-fluence and high-flux performance characteristics of the superconducting Magnum-PSI linear plasma facility

The effect of high-flux H plasma exposure with simultaneous transient heat loads on tungsten surface damage and power handling

Collective Thomson scattering system for determination of ion properties in a high flux plasma beam

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