Search Results - "Majeski, R"

Observation of Flat Electron Temperature Profiles in the Lithium Tokamak Experiment by Boyle, D P, Majeski, R, Schmitt, J C, Hansen, C, Kaita, R, Kubota, S, Lucia, M, Rognlien, T D

“…It has been predicted for over a decade that low-recycling plasma-facing components in fusion devices would allow high edge temperatures and flat or nearly…”
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Quantitative Measurement of Positive and Negative Ion Species Ejected from a Li–O–H Surface by Hydrogen and Noble Gas Ion Irradiation by Abe, S., Ostrowski, E. T., Maan, A., Krstic, P., Majeski, R., Koel, B. E.

“…We report sputtering yields of Li + , H − , O − , and OH x − ion species from an Li–O–H surface for H, D, He, Ne, and Ar ion irradiation at 45° incidence in…”
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Investigating the role of edge neutrals in exciting tearing mode activity and achieving flat temperature profiles in LTX-β by Banerjee, Santanu, Boyle, D.P., Maan, A., Ferraro, N., Wilkie, G., Majeski, R., Podesta, M., Bell, R., Hansen, C., Capecchi, W., Elliott, D.

“…Abstract We present observations, numerical simulations, and analysis from experiments in the Lithium Tokamak Experiment-Beta (LTX- β ) in which the electron…”
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The development of a Sustained High Power Density (SHPD) facility by Brown, T., Menard, J.E., Zhai, Y., Majeski, R., Rana, C., McIntyre, P.

“…A Sustained High Power Density (SHPD) facility is being planned within the U.S. as a non DT device which can be a bridge to a Compact Fusion Pilot Plant (CFPP)…”
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Extending the low-recycling, flat temperature profile regime in the lithium tokamak experiment-β (LTX-β) with ohmic and neutral beam heating by Boyle, D.P., Anderson, J., Banerjee, S., Bell, R.E., Capecchi, W., Elliott, D.B., Hansen, C., Kubota, S., LeBlanc, B.P., Maan, A., Maingi, R., Majeski, R., Menard, J.E., Oliva, S., Rhodes, T., Soukhanovskii, V., Zakharov, L.

“…Abstract Recent experiments in the lithium tokamak experiment- β (LTX- β ) have extended the duration, performance, operating conditions, and diagnosis of the…”
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Enhanced energy confinement and performance in a low-recycling tokamak by Majeski, R, Doerner, R, Gray, T, Kaita, R, Maingi, R, Mansfield, D, Spaleta, J, Soukhanovskii, V, Timberlake, J, Zakharov, L

“…Extensive lithium wall coatings and liquid lithium plasma-limiting surfaces reduce recycling, with dramatic improvements in Ohmic plasma discharges in the…”
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Improved neutral and plasma density control with increasing lithium wall coatings in the Lithium Tokamak Experiment-β (LTX-β) by Maan, A., Boyle, D.P., Majeski, R., Banerjee, S., Francisquez, M., Kaita, R., Wilkie, G.J., Capecchi, W., Kubota, S., Hansen, C., Soukhanovskii, V.

“…A comparison of three sets of Lithium Tokamak Experiment-β (LTX-β) discharges is presented, each with progressively more lithium evaporatively deposited on the…”
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Dependence of LTX plasma performance on surface conditions as determined by in situ analysis of plasma facing components by Lucia, M., Kaita, R., Majeski, R., Bedoya, F., Allain, J.P., Abrams, T., Bell, R.E., Boyle, D.P., Jaworski, M.A., Schmitt, J.C.

“…The Materials Analysis and Particle Probe (MAPP) diagnostic has been implemented on the Lithium Tokamak Experiment (LTX) at PPPL, providing the first in situ…”
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Design of the Flowing LIquid Torus (FLIT) by Kolemen, E., Hvasta, M., Majeski, R., Maingi, R., Brooks, A., Kozub, T.

“…•Flowing LIquid metal Torus, FLIT, a fast-flowing liquid metal divertor experiments, was designed to be installed at Princeton Plasma Physics Laboratory,…”
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Hydrogen retention in lithium on metallic walls from “in vacuo” analysis in LTX and implications for high-Z plasma-facing components in NSTX-U by Kaita, R., Lucia, M., Allain, J.P., Bedoya, F., Bell, R., Boyle, D., Capece, A., Jaworski, M., Koel, B.E., Majeski, R., Roszell, J., Schmitt, J., Scotti, F., Skinner, C.H., Soukhanovskii, V.

“…The application of lithium to plasma-facing components (PFCs) has long been used as a technique for wall conditioning in magnetic confinement devices to…”
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Macroscopic motion of liquid metal plasma facing components in a diverted plasma by Jaworski, M.A., Gerhardt, S.P., Morley, N.B., Abrams, T., Kaita, R., Kallman, J., Kugel, H., Majeski, R., Ruzic, D.N.

“…Liquid metal plasma facing components (PFCs) have been identified as an alternative material for fusion plasma experiments. The use of a liquid conductor where…”
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Design and calibration of a retarding field energy analyzer for the LTX-β scrape off layer and modeling of electrostatic potential in a collisionless SOL by Zhang, X., Elliott, D.B., Maan, A., Boyle, D.P., Kaita, R., Majeski, R.

“…•Li coated walls produced a collisionless scrape off layer.•Ions are mirror-trapped in a collisionless scrape off layer.•Ambipolar potential is significantly…”
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Experimental studies of lithium-based surface chemistry for fusion plasma-facing materials applications by Allain, J.P., Rokusek, D.L., Harilal, S.S., Nieto-Perez, M., Skinner, C.H., Kugel, H.W., Heim, B., Kaita, R., Majeski, R.

“…Lithium has enhanced the operational performance of fusion devices such as: TFTR, CDX-U, FTU, T-11 M, and NSTX. Lithium in the solid and liquid state has been…”
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Capillary wicking of liquid lithium on laser textured surfaces for plasma facing components by Lin, T.F., Palmer, T.A., Meinert, K.C., Murray, N.R., Majeski, R.

“…Liquid lithium has been proposed as a coating for plasma facing components (PFC) in fusion reactors in order to reduce recycling and protect the PFCs from high…”
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Results and future plans of the Lithium Tokamak eXperiment (LTX) by Schmitt, J.C., Abrams, T., Baylor, L.R., Berzak Hopkins, L., Biewer, T., Bohler, D., Boyle, D., Granstedt, E., Gray, T., Hare, J., Jacobson, C.M., Jaworski, M., Kaita, R., Kozub, T., LeBlanc, B., Lundberg, D.P., Lucia, M., Maingi, R., Majeski, R., Merino, E., Ryou, A., Shi, E., Squire, J., Stotler, D., Thomas, C.E., Tritz, K., Zakharov, L.

“…The Lithium Tokamak eXperiment (LTX) is a spherical tokamak with the unique capability of studying the low-recycling regime by coating nearly 90% of the first…”
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Low recycling regime in ITER and the LiWall concept for its divertor by Zakharov, L.E., Blanchard, W., Kaita, R., Kugel, H., Majeski, R., Timberlake, J.

“…The low recycling regime, although never considered as an option for ITER, may suggest a solution to its important issues, such as edge localized modes, plasma…”
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Effect of lithium PFC coatings on NSTX density control by Kugel, H.W., Bell, M.G., Bell, R., Bush, C., Gates, D., Gray, T., Kaita, R., Leblanc, B., Maingi, R., Majeski, R., Mansfield, D., Mueller, D., Paul, S., Raman, R., Roquemore, A.L., Sabbagh, S., Skinner, C.H., Soukhanovskii, V., Stevenson, T., Zakharov, L.

“…Lithium coatings on the graphite plasma facing components (PFCs) in NSTX are being investigated as a tool for density profile control and reducing the…”
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Lithium as a plasma facing component to optimize the edge plasma by Maingi, R., Majeski, R., Menard, J. E., Jaworski, M. A., Kaita, R.

“…The use of lithium to coat plasma-facing components (PFCs) or serve directly as liquid PFCs has resulted in energy confinement improvement in several devices…”
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Physics design requirements for the National Spherical Torus Experiment liquid lithium divertor by Kugel, H.W., Bell, M., Berzak, L., Brooks, A., Ellis, R., Gerhardt, S., Harjes, H., Kaita, R., Kallman, J., Maingi, R., Majeski, R., Mansfield, D., Menard, J., Nygren, R.E., Soukhanovskii, V., Stotler, D., Wakeland, P., Zakharov, L.E.

“…Recent National Spherical Tokamak Experiment (NSTX) high-power divertor experiments have shown significant and recurring benefits of solid lithium coatings on…”
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Controlled optimization of mode conversion from electron Bernstein waves to extraordinary mode in magnetized plasma by Jones, B, Efthimion, P C, Taylor, G, Munsat, T, Wilson, J R, Hosea, J C, Kaita, R, Majeski, R, Maingi, R, Shiraiwa, S, Spaleta, J, Ram, A K

“…In the CDX-U spherical torus, agreement between radiation temperature and Thomson scattering electron temperature profiles indicates approximately 100%…”
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