Basic physical processes and reduced models for plasma detachment von Stangeby, P C

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Physics basis and design of the ITER plasma-facing components von 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.

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The Chodura sheath for angles of a few degrees between the magnetic field and the surface of divertor targets and limiters von Stangeby, P.C.

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Influence of the E  ×  B drift in high recycling divertors on target asymmetries von Chankin, A V, Corrigan, G, Groth, M, Stangeby, P C

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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 von 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

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Accounting for Debye sheath expansion for proud Langmuir probes in magnetic confinement fusion plasmas von Tsui, C. K., Boedo, J. A., Stangeby, P. C.

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Reversed-direction 2-point modelling applied to divertor conditions in DIII-D von Nichols, J H, Stangeby, P C, McLean, A G, Canik, J M, Moser, A L, Shafer, M W, Wang, H Q

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Modelling of beryllium erosion–redeposition on ITER first wall panels von Carpentier, S., Pitts, R.A., Stangeby, P.C., Elder, J.D., Kukushkin, A.S., Lisgo, S., Fundamenski, W., Moulton, D.

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Impact of ELM control techniques on tungsten sputtering in the DIII-D divertor and extrapolations to ITER von Abrams, T., Unterberg, E. A., Rudakov, D. L., Leonard, A. W., Schmitz, O., Shiraki, D., Baylor, L. R., Stangeby, P. C., Thomas, D. M., Wang, H. Q.

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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 von 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

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Measurements of multiple heat flux components at the divertor target by using surface eroding thermocouples (invited) von Ren, J., Donovan, D. C., Watkins, J. G., Wang, H. Q., Lasnier, C., Looby, T., Canik, J., Rudakov, D., Stangeby, P. C., Thomas, D., Boivin, R.

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First wall power flux management during plasma current ramp-up on ITER von Pitts, R.A., Gribov, Y., Coburn, J., Fuentes, F.J., Severino, G., Vayakis, G., Amoskov, V., Brank, M., Carpentier, S., D’Amico, G., Dubrov, M.L., Fernández-Marina, F., Jong, C., Kavin, A.A., Khayrutdinov, R., Kocan, M., Lamzin, E., Loarte, A., Kos, L., Lukash, V.E., Mitchell, N., Raffray, A.R., Simič, G., Stangeby, P.C., Sytchevsky, S.

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A full tungsten divertor for ITER: Physics issues and design status von 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.

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Developing solid-surface plasma facing components for pilot plants and reactors with replenishable wall claddings and continuous surface conditioning. Part A: concepts and question... von Stangeby, P C, Unterberg, E A, Davis, J W, Abrams, T, Bortolon, A, Bykov, I, Donovan, D, Guo, H Y, Kolasinski, R, Leonard, A W, Nichols, J H, Rudakov, D L, Sinclair, G, Thomas, D M, Watkins, J G

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The relation between upstream density and temperature widths in the scrape-off layer and the power width in an attached divertor von Stangeby, P.C, Canik, J.M, Whyte, D.G

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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 von Ma, X, Abrams, T, Covele, B, Elder, J D, Guo, H Y, Guterl, J, Stangeby, P C

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SOLPS modeling of the effect on plasma detachment of closing the lower divertor in DIII-D von Sang, C F, Stangeby, P C, Guo, H Y, Leonard, A W, Covele, B, Lao, L L, Moser, A L, Thomas, D M

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A three-dimensional analytic model for discrete limiters in ITER von Stangeby, P.C

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Narrow heat flux channels in the COMPASS limiter scrape-off layer von 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.

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Status of the ITER full-tungsten divertor shaping and heat load distribution analysis von 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

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