Results 1 to 10 of about 2,890 (280)

Divertor shaping with neutral baffling as a solution to the tokamak power exhaust challenge [PDF]

Communications Physics
Exhausting power from the hot fusion core to the plasma-facing components is one fusion energy’s biggest challenges. The MAST Upgrade tokamak uniquely integrates strong containment of neutrals within the exhaust area (divertor) with extreme divertor ...
Kevin Verhaegh, James Harrison, David Moulton, Bruce Lipschultz, Nicola Lonigro, Nick Osborne, Peter Ryan, Christian Theiler, Tijs Wijkamp, Dominik Brida, Cyd Cowley, Gijs Derks, Rhys Doyle, Fabio Federici, Bob Kool, Olivier Février, Antti Hakola, Stuart Henderson, Holger Reimerdes, Andrew Thornton, Nicola Vianello, Marco Wischmeier, Lingyan Xiang, the EUROfusion Tokamak Exploitation Team, the MAST Upgrade Team   +24 more
doaj   +2 more sources

Recent DIII-D progress toward validating models of tungsten erosion, re-deposition, and migration for application to next-step fusion devices

Materials Research Express, 2023
Fundamental mechanisms governing the erosion and prompt re-deposition of tungsten impurities in tokamak divertors are identified and analyzed to inform the lifetime of tungsten plasma-facing components in ITER and other future devices.
T Abrams, J G Guterl, S Abe, D C Donovan, I Bykov, C A Johnson, J H Nichols, J D Elder, D A Ennis, S D Loch, D L Rudakov, G Sinclair, C H Skinner, P C Stangeby, D M Thomas, E A Unterberg, W R Wampler   +16 more
doaj   +1 more source

Energy and particle balance during plasma detachment in a long-leg divertor configuration

Nuclear Fusion, 2023
Comprehensive studies of energy and particle balances in the transition to plasma detachment in an alternative divertor configuration with long outer legs are shown.
R. Masline, S.I. Krasheninnikov
doaj   +1 more source

Preliminary analysis of alternative divertors for DEMO

Nuclear Materials and Energy, 2021
A physics and engineering analysis of alternative divertor configurations is carried out by examining benefits and problems by comparing the baseline single null solution with a Snowflake, an X- and a Super-X divertor.
F. Militello, L. Aho-Mantila, R. Ambrosino, T. Body, H. Bufferand, G. Calabro, G. Ciraolo, D. Coster, G. Di Gironimo, P. Fanelli, N. Fedorczak, A. Herrmann, P. Innocente, R. Kembleton, J. Lilburne, T. Lunt, D. Marzullo, S. Merriman, D. Moulton, A.H. Nielsen, J. Omotani, G. Ramogida, H. Reimerdes, M. Reinhart, P. Ricci, F. Riva, A. Stegmeir, F. Subba, W. Suttrop, P. Tamain, M. Teschke, A. Thrysoe, W. Treutterer, S. Varoutis, M. Wensing, A. Wilde, M. Wischmeier, L.Y. Xiang   +37 more
doaj   +1 more source

On the prediction and monitoring of tungsten prompt redeposition in tokamak divertors

Nuclear Materials and Energy, 2021
As net erosion of tungsten plasma-facing components in tokamak divertors is strongly reduced by tungsten prompt redeposition, predicting and monitoring tungsten prompt redeposition is crucial to estimate the lifetime of tungsten PFCs and the source of ...
J. Guterl, I. Bykov, R. Ding, P. Snyder
doaj   +1 more source

SOLPS-ITER analysis of a proposed STEP double null geometry: impact of the degree of disconnection on power-sharing

Nuclear Fusion, 2023
To mitigate the issue of plasma exhaust in reactor scale tight aspect ratio tokamaks such as Spherical Tokamak for Energy Production (STEP), a double-null (DN) configuration is thought to be advantageous over a single-null (SN) configuration.
R.T. Osawa, D. Moulton, S.L. Newton, S.S. Henderson, B. Lipschultz, A. Hudoba   +5 more
doaj   +1 more source

Study of the double null divertor configuration in DTT

Nuclear Materials and Energy, 2021
On the way to the development of a fusion reactor based on the Tokamak configuration, the Divertor Test Tokamak facility (DTT) [1] in construction in Italy should provide useful information for the DEMO [2] reactor in the field of the power and particle ...
P. Innocente, L. Balbinot, H. Bufferand, G. Ciraolo   +3 more
doaj   +1 more source

Transport and divertor properties of the Dynamic Ergodic Divertor [PDF]

Plasma Physics and Controlled Fusion, 2005
The concept of the dynamic ergodic divertor (DED) is based on plasma edge ergodization by a resonant perturbation. Such a divertor concept is closely related to helical or island divertors in stellerators. The base mode of the DED perturbation field can be m/n = 12/4, 6/2 or 3/1.
Lehnen, M., Abdullaev, S. S., Jachmich, S., Jakubowski, M. W., Jaspers, R., Koslowski, H. R., Krämer-Flecken, A., Kikuchi, Y., Liang, Y., Loozen, X., Pospieszczyk, A., van Rumpuy, T., Biel, W., Reiter, D., Samm, U., Schmitz, O., Sergienko, G., Tokar, M., Unterberg, B., Wolf, R., Zimmermann, O., de Bock, M. F. M., Brezinsek, S., Busch, C., Classen, I., Finken, K. H., Harting, D., von Hellermann, M.   +27 more
  +5 more sources

ELM temperature in JET and COMPASS tokamak divertors

Nuclear Fusion, 2023
Analysis of the divertor edge localized mode (ELM) electron temperature at a uniquely high temporal resolution (10 ^−5 s) was reported at the JET tokamak (Guillemaut et al 2018 Nucl. Fusion 58 066006).
J. Horacek, D. Tskhakaya, J. Cavalier, J. Adamek, A.C. Mana, L. Frassinetti, A. Beltrami, S. Lukes, S. Aleiferis, G. Matthews, M. Komm, P. Bilkova, JET Contributors, COMPASS Team   +13 more
doaj   +1 more source

Innovative Tungsten Coatings for an Application in Modern and Future Fusion Devices

Metals, 2023
Tungsten is foreseen presently as the plasma-facing material for divertors in fusion power plants. In order to achieve durable operation of divertors of current fusion reactors, an efficient way of maintaining the divertor functionality is needed.
Tom Keller, Andrey Litnovsky, Georg Mauer, Christian Linsmeier, Olivier Guillon   +4 more
doaj   +1 more source