2018
DOI: 10.1016/j.fusengdes.2018.03.033
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Operational characteristics of the superconducting high flux plasma generator Magnum-PSI

Abstract: The interaction of intense plasma impacting on the wall of a fusion reactor is an area of high and increasing importance in the development of electricity production from nuclear fusion. In the Magnum-PSI linear device, an axial magnetic field confines a high density, low temperature plasma produced by a wall stabilized DC cascaded arc into an intense magnetized plasma beam directed onto a target. The experiment has shown its capability to reach conditions that enable fundamental studies of plasma-surface inte… Show more

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Cited by 16 publications
(11 citation statements)
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“…The quasi continuous plasma exposures were performed in Magnum-PSI (with interruption for realignment of diagnostics and during the night) [2,3,6]. Details for the six exposures are given in Tab.…”
Section: Magnum Exposurementioning
confidence: 99%
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“…The quasi continuous plasma exposures were performed in Magnum-PSI (with interruption for realignment of diagnostics and during the night) [2,3,6]. Details for the six exposures are given in Tab.…”
Section: Magnum Exposurementioning
confidence: 99%
“…A small-scale mockup of the ITER divertor plasma-facing units, consisting of seven tungsten monoblocks brazed on to a CuCrZr cooling tube, was exposed to a variety of high fluence, high flux plasma loads in Magnum-PSI [2,3,6]. Six exposures were performed including H, He, D and D:He (95:5) plasmas with low electron temperature (1.5-5 eV) and high electron density (1×10 20 -2×10 21 m -3 ), resulting in a maximum surface temperature in the range 750-1600 °C (Tab.…”
Section: Conclusion and Summarymentioning
confidence: 99%
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“…Different diagnostics are applied during a typical operation of Magnum-PSI, including Thomson Scattering near the target [5]. In a typical Magnum-PSI run, a Hydrogen plasma is generated at the source chamber by a cascaded arc source [6].…”
Section: Introductionmentioning
confidence: 99%
“…In order to comply to the safety regulations, the total retained tritium (T) in the reactor vessel should be monitored to assure that the amount of tritium in the ITER vessel does not exceed the limit of 700 g. ITER will use two hydrogen isotopes, deuterium D and tritium T to fuel the fusion reaction. The fuel retention in ITER divertor walls exposed with plasma fluxes up to 10 24 ions/m 2 s can be systematically studied in the linear plasma devices with D plasma [4,5]. The retention is strongly influenced by the properties of wall materials, i.e.…”
Section: Introductionmentioning
confidence: 99%