Search Results - "Stangeby, C"

Physics basis and design of the ITER plasma-facing components by Pitts, R.A., Carpentier, S., Escourbiac, F., Hirai, T., Komarov, V., Kukushkin, A.S., Lisgo, S., Loarte, A., Merola, M., Mitteau, R., Raffray, A.R., Shimada, M., Stangeby, P.C.

“…In ITER, as in any tokamak, the first wall and divertor plasma-facing components (PFC) must provide adequate protection of in-vessel structures, sufficient…”
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First Evidence of Local E×B Drift in the Divertor Influencing the Structure and Stability of Confined Plasma near the Edge of Fusion Devices by Wang, H Q, Guo, H Y, Xu, G S, Leonard, A W, Wu, X Q, Groth, M, Jaervinen, A E, Watkins, J G, Osborne, T H, Thomas, D M, Eldon, D, Stangeby, P C, Turco, F, Xu, J C, Wang, L, Wang, Y F, Liu, J B

“…The structure of the edge plasma in a magnetic confinement system has a strong impact on the overall plasma performance. We uncover for the first time a…”
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Design and physics basis for the upcoming DIII-D SAS-VW campaign to quantify tungsten leakage and transport in a new slot divertor geometry by Abrams, T, Sinclair, G, Nichols, J H, Unterberg, E A, Donovan, D C, Duran, J, Elder, J D, Glass, F, Grierson, B A, Guo, H Y, Hall, T, Ma, X, Maurizio, R, McLean, A G, Murphy, C, Nguyen, R, Rudakov, D L, Stangeby, P C, Thomas, D M, Zamperini, S A

“…Abstract A set of experiments are planned to exploit the high SOL collisionality enabled by a tightly baffled slot divertor geometry to suppress tungsten…”
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Status of the ITER full-tungsten divertor shaping and heat load distribution analysis by Carpentier-Chouchana, S, Hirai, T, Escourbiac, F, Durocher, A, Fedosov, A, Ferrand, L, Firdaouss, M, Kocan, M, Kukushkin, A S, Jokinen, T, Komarov, V, Lehnen, M, Merola, M, Mitteau, R, Pitts, R A, Stangeby, P C, Sugihara, M

“…In September 2011, the ITER Organization (IO) proposed to begin operation with a full-tungsten (W) armoured divertor, with the objective of taking a decision…”
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Hyperhaploidy is a novel high-risk cytogenetic subgroup in multiple myeloma by Sawyer, J R, Tian, E, Shaughnessy Jr, J D, Epstein, J, Swanson, C M, Stangeby, C, Hale, C L, Parr, L, Lynn, M, Sammartino, G, Lukacs, J L, Stein, C, Bailey, C, Zangari, M, Davies, F E, Van Rhee, F, Barlogie, B, Morgan, G J

“…Hyperhaploid clones (24–34 chromosomes) were identified in 33 patients with multiple myeloma (MM), demonstrating a novel numerical cytogenetic subgroup…”
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Recent DIII-D progress toward validating models of tungsten erosion, re-deposition, and migration for application to next-step fusion devices by Abrams, T, Guterl, J G, Abe, S, Donovan, D C, Bykov, I, Johnson, C A, Nichols, J H, Elder, J D, Ennis, D A, Loch, S D, Rudakov, D L, Sinclair, G, Skinner, C H, Stangeby, P C, Thomas, D M, Unterberg, E A, Wampler, W R

“…Abstract Fundamental mechanisms governing the erosion and prompt re-deposition of tungsten impurities in tokamak divertors are identified and analyzed to…”
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Modelling of beryllium erosion–redeposition on ITER first wall panels by Carpentier, S., Pitts, R.A., Stangeby, P.C., Elder, J.D., Kukushkin, A.S., Lisgo, S., Fundamenski, W., Moulton, D.

“…Unlike any current operating tokamak, ITER will operate long pulse, high performance discharges with an almost conformal, shaped and full beryllium first wall…”
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Analysis of a tungsten sputtering experiment in DIII-D and code/data validation of high redeposition/reduced erosion by Brooks, J.N., Elder, J.D., McLean, A.G., Rudakov, D.L., Stangeby, P.C., Wampler, W.R.

“…We analyze a DIII-D tokamak experiment where two tungsten spots on the removable DiMES divertor probe were exposed to 12s of attached plasma conditions, with…”
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Thermal management of tungsten leading edges in DIII-D by Nygren, R.E., Rudakov, D.L., Murphy, C., Watkins, J.D., Unterberg, E.A., Barton, J.L., Stangeby, P.C.

“…•Experience with tile alignment, documentation and thermal modeling are important aspects of thermal management in DIII-D.•Various approaches to leading edges…”
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SOL width in limited versus diverted discharges in DIII-D by Rudakov, D.L., Boedo, J.A., Pitts, R.A., Jackson, G.L., Lasnier, C.J., Leonard, A.W., Moyer, R.A., Stangeby, P.C., Tynan, G.R., Watkins, J.G.

“…An experiment aimed at benchmarking the ITER scrape-off layer (SOL) power width scaling in limited L-mode discharges has been conducted on DIII-D. Scans of the…”
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3D-DIVIMP(HC) code modeling of DIII-D DiMES porous plug injector experiments by Mu, Y., Elder, J.D., Stangeby, P.C., McLean, A.G.

“…A Porous Plug Injector (PPI) system for the Divertor Material Evaluation System (DiMES) on DIII-D has been employed for in situ study of chemical erosion in…”
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Quantification of chemical erosion in the DIII-D divertor and implications for ITER by McLean, A.G., Stangeby, P.C., Bray, B.D., Brezinsek, S., Brooks, N.H., Davis, J.W., Isler, R.C., Kirschner, A., Laengner, R., Lasnier, C.J., Mu, Y., Munoz, J., Rudakov, D.L., Schmitz, O., Unterberg, E.A., Watkins, J.G., Whyte, D.G., Wong, C.P.C.

“…The Porous Plug Injector (PPI) has proven to be an invaluable diagnostic for in situ characterization and quantification of erosion phenomena in DIII-D…”
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Evaluation of the impact of divertor closure on high-Z material transport and leakage in small angle slot divertor with toroidal tungsten rings in DIII-D by Ma, X, Abrams, T, Covele, B, Elder, J D, Guo, H Y, Guterl, J, Stangeby, P C

“…Predictive modeling of the closed Small Angle Slot (SAS) divertor with toroidal tungsten (W) rings in different poloidal locations is conducted to evaluate the…”
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First tests of diagnostic mirrors in a tokamak divertor: An overview of experiments in DIII-D by Litnovsky, A., Rudakov, D.L., De Temmerman, G., Wienhold, P., Philipps, V., Samm, U., McLean, A.G., West, W.P., Wong, C.P.C., Brooks, N.H., Watkins, J.G., Wampler, W.R., Stangeby, P.C., Boedo, J.A., Moyer, R.A., Allen, S.L., Fenstermacher, M.E., Groth, M., Lasnier, C.J., Boivin, R.L., Leonard, A.W., Romanyuk, A., Hirai, T., Pintsuk, G., Breuer, U., Scholl, A.

“…Mirrors will be used in ITER in all optical diagnostic systems observing the plasma radiation in the ultraviolet, visible and infrared ranges. Diagnostic…”
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A full tungsten divertor for ITER: Physics issues and design status by Pitts, R.A., Carpentier, S., Escourbiac, F., Hirai, T., Komarov, V., Lisgo, S., Kukushkin, A.S., Loarte, A., Merola, M., Sashala Naik, A., Mitteau, R., Sugihara, M., Bazylev, B., Stangeby, P.C.

“…Budget restrictions have forced the ITER Organization to reconsider the baseline divertor strategy, in which operations would begin with carbon (C) in the high…”
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Narrow heat flux channels in the COMPASS limiter scrape-off layer by Horacek, J., Vondracek, P., Panek, R., Dejarnac, R., Komm, M., Pitts, R.A., Kocan, M., Goldston, R.J., Stangeby, P.C., Gauthier, E., Hacek, P., Havlicek, J., Hron, M., Imrisek, M., Janky, F., Seidl, J.

“…The ITER first wall is designed for start-up and ramp-down in limiter configuration. The wall panels are toroidally shaped in order to spread the incident…”
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Plasma interactions with the outboard chamber wall in DIII-D by Rudakov, D.L., Boedo, J.A., Yu, J.H., Brooks, N.H., Fenstermacher, M.E., Groth, M., Hollmann, E.M., Lasnier, C.J., McLean, A.G., Moyer, R.A., Stangeby, P.C., Tynan, G.R., Wampler, W.R., Watkins, J.G., West, W.P., Wong, C.P.C., Bastasz, R.J., Buchenauer, D., Whaley, J.

“…Erosion of the main chamber plasma-facing components is of concern for ITER. Plasma interaction with the outboard chamber wall is studied in DIII-D using…”
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Characterization of chemical sputtering using the Mark II DiMES porous plug injector in attached and semi-detached divertor plasmas of DIII-D by McLean, A.G., Davis, J.W., Stangeby, P.C., Allen, S.L., Boedo, J.A., Bray, B.D., Brezinsek, S., Brooks, N.H., Fenstermacher, M.E., Groth, M., Haasz, A.A., Hollmann, E.M., Isler, R.C., Lasnier, C.J., Mu, Y., Petrie, T.W., Rudakov, D.L., Watkins, J.G., West, W.P., Whyte, D.G., Wong, C.P.C.

“…An improved, self-contained gas injection system for the divertor material evaluation system (DiMES) on DIII-D has been employed for in situ study of chemical…”
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3D-DIVIMP-HC modeling analysis of methane injection into DIII-D using the DiMES porous plug injector by Mu, Y., McLean, A.G., Elder, J.D., Stangeby, P.C., Bray, B.D., Brooks, N.H., Davis, J.W., Fenstermacher, M.E., Groth, M., Lasnier, C.J., Rudakov, D.L., Watkins, J.G., West, W.P., Wong, C.P.C.

“…A self-contained gas injection system for the Divertor Material Evaluation System (DiMES) on DIII-D, the porous plug injector (PPI), has been employed for in…”
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OSM-EIRENE modeling of neutral pressures in the Alcator C-Mod divertor by Lisgo, S., Börner, P., Boswell, C., Elder, D., LaBombard, B., Lipschultz, B., Pitcher, C.S., Reiter, D., Stangeby, P.C., Terry, J.L., Wiesen, S.

“…The ITER divertor will be more collisional than divertors in existing tokamaks and the neutral modeling tools used for predictive ITER modeling need to be…”
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