Extreme hydrogen plasma fluxes at Pilot-PSI enter the ITER divertor regime

Groot, B. de; Al, R.S.; Engeln, Rah Richard; Goedheer, W. J.; Kruijt, O.G.; Meiden, H.J. van der; Prins, P.R.; Schram, D.C.; Smeets, P.H.M.; Veremiyenko, V.P.; Vijvers, W.A.J.; Westerhout, J.; Kleyn, Aart W.; Cardozo, N.J. Lopes; Rooij, G.J. van

doi:10.1016/j.fusengdes.2007.07.052

Cited by 31 publications

(20 citation statements)

References 6 publications

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“…During the normal operation, in the ITER divertor zone steady state plasma parameters are expected to be $5-20 MW m À2 heat, $10 24 H + m À2 s À1 (1-10 eV) protons, and $10 22 -10 24 He 2+ m À2 s À1 (<500 eV) helium ions [1][2][3]. In contrast, a 10 m radius IFE chamber, such as the high average power laser (HAPL) reactor [4] is expected to be exposed to helium and deuterium ions ranging in energy from 1 keV to 10 MeV, with a low energy helium flux of about $10 15 m À2 in the range of 100-200 keV and a high energy helium flux of $10 16 m À2 between 200 keV and 10 MeV (per shot from a 365 MJ target).…”

Section: Introductionmentioning

confidence: 99%

A description of stress driven bubble growth of helium implanted tungsten

Sharafat

Takahashi

Nagasawa

et al. 2009

Journal of Nuclear Materials

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Section: Introductionmentioning

confidence: 99%

A description of stress driven bubble growth of helium implanted tungsten

Sharafat

Takahashi

Nagasawa

et al. 2009

Journal of Nuclear Materials

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“…Usually, a strong magnetic field of more than about 0.1 T is employed in linear plasma devices [4–8,13–16] for the radial confinement of the produced plasma. The electric power required for energizing the magnetic coils is sometimes very large.…”

Section: Device Specificationmentioning

confidence: 99%

“…We therefore need some test facilities to investigate the material properties of a tungsten wall from various points of view under reactor‐relevant conditions. Several linear plasma simulators [12–16] have been working for the above purposes, including NAGDIS‐I and II. A compact plasma device for such plasma–wall interaction (PWI) studies is very helpful to investigate, for example, how to avoid the helium damage of tungsten surface, what the surface characteristics for nanostructured tungsten surface are, and a possible utilization of such nanostructured tungsten with the suppression of induced arcing.…”

Section: Introductionmentioning

confidence: 99%

Characteristics of the compact plasma device AIT‐PID with multicusp magnetic confinement

Takamura

2012

IEEJ Transactions Elec Engng

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A unique plasma-generation device called the "Aichi Institute of Technology-Plasma Irradiation Device" has been developed for plasma-wall interaction (PWI) studies toward realization of a fusion reactor. It has power-saving characteristics as well as compactness due to the employment of a multicusp magnetic field configuration instead of a strong axial magnetic field. Helium as well as argon plasmas are generated, showing an outstanding property of production of the hot-electron component which can be controlled by changing the working gas pressure. Utilizing such outstanding properties, some typical studies on PWI are introduced. An azimuthally asymmetric confinement depending on the direction of magnetic field lines, particularly for energetic electrons, has been found. Some discussions on the physical mechanisms are given.

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“…A prototype setup named Pilot-PSI is operational at FOM Rijnhuizen and has achieved record plasma parameters of n e =4ϫ 10 21 m −3 with T e = 2 eV in an ϳ2 cm wide beam confined by B Ͻ 1.6 T. [11][12][13] This machine is used as a test bed for the development of technologies for Magnum-PSI, e.g., the rf heating system, 14 source development, 15 and diagnostics. 16 The plasma is produced with a wall stabilized dc cascaded arc 17 and expands supersonically into a vacuum vessel kept at low pressure ͑Ͻ10 Pa͒.…”

Section: Introductionmentioning

confidence: 99%

Modeling and experiments on differential pumping in linear plasma generators operating at high gas flows

Eck

Koppers

Rooij

et al. 2009

Journal of Applied Physics

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The direct simulation Monte Carlo ͑DSMC͒ method was used to investigate the efficiency of differential pumping in linear plasma generators operating at high gas flows. Skimmers are used to separate the neutrals from the plasma beam, which is guided from the source to the target by a strong axial magnetic field. In this way, the neutrals are prevented to reach the target region. The neutral flux to the target must be lower than the plasma flux to enable ITER relevant plasma-surface interaction ͑PSI͒ studies. It is therefore essential to control the neutral gas dynamics. The DSMC method was used to model the expansion of a hot gas in a low pressure vessel where a small discrepancy in shock position was found between the simulations and a well-established empirical formula. Two stage differential pumping was modeled and applied in the linear plasma devices Pilot-PSI and PLEXIS. In Pilot-PSI a factor of 4.5 pressure reduction for H 2 has been demonstrated. Both simulations and experiments showed that the optimum skimmer position depends on the position of the shock and therefore shifts for different gas parameters. The shape of the skimmer has to be designed such that it has a minimum impact on the shock structure. A too large angle between the skimmer and the forward direction of the gas flow leads to an influence on the expansion structure. A pressure increase in front of the skimmer is formed and the flow of the plasma beam becomes obstructed. It has been shown that a skimmer with an angle around 53°gives the best performance. The use of skimmers is implemented in the design of the large linear plasma generator Magnum-PSI. Here, a three stage differentially pumped vacuum system is used to reach low enough neutral pressures near the target, opening a door to PSI research in the ITER relevant regime.

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Extreme hydrogen plasma fluxes at Pilot-PSI enter the ITER divertor regime

Cited by 31 publications

References 6 publications

A description of stress driven bubble growth of helium implanted tungsten

A description of stress driven bubble growth of helium implanted tungsten

Characteristics of the compact plasma device AIT‐PID with multicusp magnetic confinement

Modeling and experiments on differential pumping in linear plasma generators operating at high gas flows

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