Search Results - "Lisgo, S W"

Design assessment of ITER port plug plasma facing material options by Lisgo, S.W., Börner, P., Kukushkin, A., Pitts, R.A., Polevoi, A., Reiter, D.

“…The objective of this computational engineering design study is to assess whether the ITER confined plasma will be adversely affected if the diagnostic port…”
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First results on modeling of ITER infrared images by Ko an, M, Reichle, R, Aumeunier, M-H, Gunn, J P, Kajita, S, Le Guern, F, Lisgo, S W, Loarer, T, Kukushkin, A S, Sashala Naik, A, Rigollet, F, Stratton, B

“…Infrared (IR) images of the ITER wide angle viewing system are modeled for the baseline plasma equilibrium and partially detached tungsten divertor, taking…”
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The new SOLPS-ITER code package by Wiesen, S., Reiter, D., Kotov, V., Baelmans, M., Dekeyser, W., Kukushkin, A.S., Lisgo, S.W., Pitts, R.A., Rozhansky, V., Saibene, G., Veselova, I., Voskoboynikov, S.

“…The SOLPS-ITER package represents a renewed coupling of the up-to-date parallelized EIRENE Monte-Carlo code and the B2.5 edge plasma solver. Each part of the…”
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Characterisation of detached plasmas on the MAST tokamak by Harrison, J.R., Lisgo, S.W., Gibson, K.J., Tamain, P., Dowling, J., The MAST Team

“…Divertor detachment is an attractive operating regime for the next generation of tokamak devices, as it offers a means of mitigating the steady-state heat flux…”
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Disruption mitigation studies on the Mega Amp Spherical Tokamak (MAST) by Thornton, A.J., Gibson, K.J., Harrison, J.R., Kirk, A., Lisgo, S.W., Lehnen, M., Martin, R., Naylor, G., Scannell, R., Cullen, A.

“…Disruptions pose a significant challenge in future devices where the increased stored energy can lead to unacceptably large transient heat loads on plasma…”
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Quantitative modeling of fuel retention in the JET-C and JET-ILW wall configurations by WallDYN and predictions for ITER by Schmid, K., Krieger, K., Lisgo, S.W., Meisl, G., Brezinsek, S.

“…The hydrogenic fuel retention in ITER will be dominated by co-deposition. Therefore predictions of retention in ITER require a global model of migration of…”
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Design assessment of tungsten as an upper panel plasma facing material in ITER by Lisgo, S.W., Kukushkin, A., Pitts, R.A., Reiter, D.

“…The objective of this computational engineering design study is to assess whether the ITER confined plasma will be adversely affected if the first wall at the…”
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Modelling ELM heat flux deposition on the ITER main chamber wall by Kočan, M., Pitts, R.A., Lisgo, S.W., Loarte, A., Gunn, J.P., Fuchs, V.

“…The interaction of ELM filaments with the ITER beryllium first wall panels (FWPs) is studied using a simple ad-hoc fluid model of the filament parallel…”
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Assessment of tungsten sources in the edge plasma of WEST by Marandet, Y., Bufferand, H., Bucalossi, J., Ciraolo, G., Lisgo, S.W., Tsitrone, E.

“…The WEST project, an on-going upgrade of Tore Supra, aims at providing the capability to test ITER relevant tungsten (W) divertor components under realistic…”
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Nitrogen retention in ASDEX Upgrade by Meisl, G., Schmid, K., Oberkofler, M., Krieger, K., Lisgo, S.W., Aho-Mantila, L., Reimold, F.

“…We investigated the transport of nitrogen through the plasma and the interaction of nitrogen with tungsten under divertor exposure conditions during…”
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Determination of Be sputtering yields from spectroscopic observations at the JET ITER-like wall based on three-dimensional ERO modelling by Borodin, D, Brezinsek, S, Miettunen, J, Stamp, M, Kirschner, A, Björkas, C, Groth, M, Marsen, S, Silva, C, Lisgo, S W, Matveev, D, Airila, M, Philipps, V

“…Estimations of the ITER first wall (FW) lifetime, previously made using the three-dimensional Monte-Carlo ERO code (Borodin et al 2011 Phys. Scr. T145 014008),…”
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Optimization of optical dumps for H-alpha spectroscopy in ITER by Andreenko, E.N., Alekseev, A.G., Kukushkin, A.B., Neverov, V.S., Lisgo, S.W., Morozov, A.A.

“…•Simulation of spectrum of deuterium Balmer-alpha divertor stray light (DSL) in ITER is carried out using Zemax OpticStudio ray tracing software.•The DSL…”
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Beryllium migration and evolution of first wall surface composition in the JET ILW configuration by Krieger, K., Brezinsek, S., Reinelt, M., Lisgo, S.W., Coenen, J.W., Jachmich, S., Marsen, S., Meigs, A., van Rooij, G., Stamp, M., van Hoey, O., Ivanova, D., Loarer, T., Philipps, V.

“…Material migration and the resulting evolution of plasma facing surfaces were studied at the beginning of the JET ILW campaign using the singular opportunity…”
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WallDYN simulations of material migration and fuel retention in ITER low power H plasmas and high power neon-seeded DT plasmas by Khan, A., De Temmerman, G., Lisgo, S.W., Bonnin, X., Anand, H., Miller, M.A., Pitts, R.A., Schmid, K., Kukushkin, A.S.

“…•Deposition and fuel retention profiles in low power hydrogen L-mode plasmas and neon (Ne) seeded ITER burning plasmas have been investigated.•In the low power…”
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Detachment evolution on the TCV tokamak by Harrison, J.R., Vijvers, W.A.J., Theiler, C., Duval, B.P., Elmore, S., Labit, B., Lipschultz, B., van Limpt, S.H.M., Lisgo, S.W., Tsui, C.K., Reimerdes, H., Sheikh, U., Verhaegh, K.H.A., Wischmeier, M.

“…•A detailed analysis of data from several diagnostics on TCV has been carried out to study divertor detachment in dedicated experiments.•The detachment “front”…”
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Asymmetry of the Balmer-alpha line shape and recovery of the effective hydrogen temperature in the tokamak scrape-off layer by Neverov, V. S., Kukushkin, A. B., Lisgo, S. W., Kukushkin, A. S., Alekseev, A. G.

“…An algorithm for recovering the effective temperature of atoms of hydrogen (and its isotopes) in the tokamak scrape-off layer from the asymmetry of the…”
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Review of the ITER diagnostics suite for erosion, deposition, dust and tritium measurements by Reichle, R., Andrew, P., Bates, P., Bede, O., Casal, N., Choi, C.H., Barnsley, R., Damiani, C., Bertalot, L., Dubus, G., Ferreol, J., Jagannathan, G., Kocan, M., Leipold, F., Lisgo, S.W., Martin, V., Palmer, J., Pearce, R., Philipps, V., Pitts, R.A., Pampin, R., Passedat, G., Puiu, A., Suarez, A., Shigin, P., Shu, W., Vayakis, G., Veshchev, E., Walsh, M.

“…Dust and tritium inventories in the vacuum vessel have upper limits in ITER that are set by nuclear safety requirements. Erosion, migration and re-deposition…”
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SOLPS-ITER Study of neutral leakage and drift effects on the alcator C-Mod divertor plasma by Dekeyser, W., Bonnin, X., Lisgo, S.W., Pitts, R.A., Brunner, Dan, LaBombard, Brian, Terry, Jim L.

“…•First fully coupled SOLPS-ITER simulations of the Alcator C-Mod divertor plasma including kinetic neutrals and drifts.•Neutral leakage through divertor…”
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Simulating the nitrogen migration in Be/W tokamaks with WallDYN by Meisl, G, Schmid, K, Krieger, K, Oberkofler, M, Lisgo, S W, contributors, JET

“…The migration of wall material or seeding impurities plays an important role in the formation of mixed materials, the impurity contamination of the plasma and…”
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Nitrogen transport in ASDEX Upgrade: Role of surface roughness and transport to the main wall by Meisl, G., Oberkofler, M., Hakola, A., Krieger, K., Schmid, K., Lisgo, S.W., Mayer, M., Lahtinen, A., Drenik, A., Potzel, S., Aho-Mantila, L., Team, ASDEX Upgrade

“…•The transport and deposition of nitrogen in ASDEX Upgrade was studied by the injection of 15N and ion beam analysis of exposed samples.•The N deposition on…”
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