DiMES contributions to PMI understanding

Wong, C.P.C.; Whyte, D.G.; Bastasz, R.; Wampler, W.R.; Brooks, J.N.; Evans, T.E.; West, W.P.; Whaley, Josh A.; Doerner, R.; Watkins, J. G.; Allain, J. P.; Hassanein, A.; Rudakov, D.L.

doi:10.1109/fusion.2003.1426629

Cited by 3 publications

(2 citation statements)

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“…These results confirm the observed differences between hydrocarbon deposition in gaps at ASDEX Upgrade and TEXTOR and agree very well with the observed temperature dependency of hydrocarbon deposition at remote surface [8]. This is possibly due to the observation that the sticking probability at least of CH 3 + hydrocarbons does not very significantly in the relevant surface temperature range, while the D and C are still deposited with approximate constant ratio of D/C≈0.7 and an exponential fall-off length from the gap entrance of ≈3mm [8]. This is a very encouraging result for ITER, suggesting that moderately elevated temperature can significantly reduce tritium accumulation in tile gaps.…”

Section: Tile-gap Experimentssupporting

confidence: 80%

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Divertor and midplane materials evaluation system in DIII-D

Wong

Rudakov

Allain

et al. 2007

Journal of Nuclear Materials

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The Divertor Materials Evaluation System (DiMES) at General Atomics has successfully advanced the understanding of plasma surface interaction phenomena involving ITERrelevant materials and it has been utilized for advanced diagnostic designs in the lower divertor of DIII-D. This paper describes a series of recent successful experiments. These include the study of carbon deposition in gaps and on metallic mirrors as a function of temperature, study of dust migration from the divertor, study of methane injection in order to benchmark chemical sputtering diagnostics, and the measurement of charge exchange neutrals with a hydrogen sensor. In concert with the modification of the lower divertor of DIII-D, the DiMES sample vertical location has been modified to match the raised divertor floor. The new Mid-plane Material Exposure Sample (MiMES) design will also be presented. MiMES will allow the study and measurement of erosion and redeposition of material at the outboard mid-plane of DIII-D, including effects from convective transport. We will continue to expose relevant materials and advanced diagnostics to different plasma configurations under various operational regimes, including material erosion and re-deposition experiments, and gaps and mirror exposures at elevated temperature.

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Section: Tile-gap Experimentssupporting

confidence: 80%

“…Material samples can be inserted into the lower divertor of DIII-D and exposed to selected plasma discharges. Net material erosion and redeposition can be measured and results can be used to benchmark modeling codes [3].…”

Section: Introductionmentioning

confidence: 99%

Divertor and midplane materials evaluation system in DIII-D

Wong

Rudakov

Allain

et al. 2007

Journal of Nuclear Materials

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The materials irradiation experiment for testing plasma facing materials at fusion relevant conditions

Garrison

Zenobia

Egle

et al. 2016

Review of Scientific Instruments

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The Materials Irradiation Experiment (MITE-E) was constructed at the University of Wisconsin-Madison Inertial Electrostatic Confinement Laboratory to test materials for potential use as plasma-facing materials (PFMs) in fusion reactors. PFMs in fusion reactors will be bombarded with x-rays, neutrons, and ions of hydrogen and helium. More needs to be understood about the interactions between the plasma and the materials to validate their use for fusion reactors. The MITE-E simulates some of the fusion reactor conditions by holding samples at temperatures up to 1000 °C while irradiating them with helium or deuterium ions with energies from 10 to 150 keV. The ion gun can irradiate the samples with ion currents of 20 μA-500 μA; the typical current used is 72 μA, which is an average flux of 9 × 10(14) ions/(cm(2) s). The ion gun uses electrostatic lenses to extract and shape the ion beam. A variable power (1-20 W), steady-state, Nd:YAG laser provides additional heating to maintain a constant sample temperature during irradiations. The ion beam current reaching the sample is directly measured and monitored in real-time during irradiations. The ion beam profile has been investigated using a copper sample sputtering experiment. The MITE-E has successfully been used to irradiate polycrystalline and single crystal tungsten samples with helium ions and will continue to be a source of important data for plasma interactions with materials.

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