Results 21 to 30 of about 447 (244)

A new scaling for divertor detachment

Plasma Physics and Controlled Fusion, 2017
The ITER design, and future reactor designs, depend on divertor 'detachment,' whether partial, pronounced or complete, to limit heat flux to plasma-facing components and to limit surface erosion due to sputtering. It would be valuable to have a measure of the difficulty of achieving detachment as a function of machine parameters, such as input power ...
R J Goldston, M L Reinke, J A Schwartz
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Understanding detachment of the W7-X island divertor

Nuclear Fusion, 2021
Abstract The fundamental behavior of the W7-X island divertor under detached conditions, which has been theoretically predicted with the EMC3-Eirene code, is re-examined here under the experimental conditions achieved so far and compared with the first experimental results.
Feng, Y., Jakubowski, M., König, R., Krychowiak, M., Otte, M., Reimold, F., Reiter, D., Schmitz, O., Zhang, D., Beidler, C., Biedermann, C., Bozhenkov, S., Brunner, K. ; https://orcid.org/0000-0002-0974-0457, Dinklage, A., Drewelow, P., Effenberg, F., Endler, M., Fuchert, G., Gao, Y., Geiger, J., Hammond, K., Helander, P., Killer, C., Knauer, J., Kremeyer, T., Pasch, E., Rudischhauser, L., Schlisio, G., Pedersen, T., Wenzel, U., Winters, V.   +30 more
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Divertor geometry effects on detachment in TCV [PDF]

Journal of Nuclear Materials, 2001
Experimental observations and some preliminary results from B2-Eirene code modelling of divertor detachment in the TCV tokamak are reported, with emphasis on the aspects of this detachment related to divertor geometry. The contribution is restricted to deuterium fuelled ohmic plasmas for which the CB drift is directed away from the X-point of lower ...
Pitts, R., Duval, B., Loarte, A., Moret, J., Boedo, J., Coster, D., Furno, I., Horacek, J., Kukushkin, A., Reiterand, D., Rommers, J.   +10 more
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Investigation of the particle accumulation effects on the power exhaust of snowflake minus divertor on HL-2M tokamak by SOLPS-ITER

Nuclear Materials and Energy, 2020
To solve the power exhaust handling challenge, meanwhile maintaining acceptable divertor target erosion, the snowflake divertor (SFD) is proposed on HL-2M tokamak. In this work, simulations are carried out by using scrape-off layer plasma simulation code
Yanjie Zhang, Chaofeng Sang, Jiaxian Li, Guoyao Zheng, Chen Zhang, Daoyuan Liu, Dezhen Wang   +6 more
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Predictive modeling of a lithium vapor box divertor in NSTX-U using SOLPS-ITER

Nuclear Materials and Energy, 2021
The unmitigated heat flux in attached operation of a fusion power plant is predicted to be destructive to any solid divertor surface. Detachment, whereby the plasma pressure drops significantly before reaching the divertor target thus greatly reducing ...
E.D. Emdee, R.J. Goldston, J.D Lore, X. Zhang   +3 more
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Poloidal Pressure Gradients, Divertor Detachment and Marfes [PDF]

Contributions to Plasma Physics, 1998
AbstractBecause the radiation power density from a marfe scales approximately as the square of its plasma pressure, and since increased radiation would aid divertor detachment for high power tokamaks, this paper identifies regions that might permit locally increased plasma pressure in steady state. The magnetic and dynamic (flow) constraints of magneto‐
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Impact of drifts on divertor power exhaust in DIII-D

Nuclear Materials and Energy, 2019
Radiative divertor experiments and 2D fluid simulations show strong impact of cross-field drifts on the low field side (LFS) divertor target heat flux and volumetric radiation profiles when evolving to detached conditions in DIII-D high confinement mode (
A.E. Jaervinen, S.L. Allen, D. Eldon, M.E. Fenstermacher, M. Groth, D.N. Hill, C.J. Lasnier, A.W. Leonard, A.G. McLean, G.D. Porter, T.D. Rognlien, C.M. Samuell, H.Q. Wang, J.G. Watkins   +13 more
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Experimental observation of heat flux mitigation during divertor detachment in the DIII-D small angle slot divertor

Nuclear Materials and Energy, 2021
Employing an array of surface eroding thermocouples (SETCs), the heat flux measured at the outer strike point of the DIII-D Small Angle Slot (SAS) divertor was found to be reduced by ~50% when the plasma reached the detachment regime compared to the ...
J. Ren, D.C. Donovan, J.G. Watkins, H.Q. Wang, D.M. Thomas, R. Boivin   +5 more
doaj   +1 more source

Heat flux management via advanced magnetic divertor configurations and divertor detachment [PDF]

Journal of Nuclear Materials, 2015
Abstract The snowflake divertor (SFD) control and detachment control to manage the heat flux at the divertor are successfully demonstrated at DIII-D. Results of the development and implementation of these two heat flux reduction control methods are presented.
Kolemen, E., Allen, S.L., Bray, B.D., Fenstermacher, M.E., Humphreys, D.A., Hyatt, A.W., Lasnier, C.J., Leonard, A.W., Makowski, M.A., McLean, A.G., Maingi, R., Nazikian, R., Petrie, T.W., Soukhanovskii, V.A., Unterberg, E.A.   +14 more
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An assessment of nitrogen concentrations from spectroscopic measurements in the JET and ASDEX upgrade divertor

Nuclear Materials and Energy, 2019
The impurity concentration in the tokamak divertor plasma is a necessary input for predictive scaling of divertor detachment, however direct measurements from existing tokamaks in different divertor plasma conditions are limited. To address this, we have
S.S. Henderson, M. Bernert, S. Brezinsek, M. Carr, M. Cavedon, R. Dux, D.S. Gahle, J. Harrison, A. Kallenbach, B. Lipschultz, B. Lomanowski, A. Meigs, M. O’Mullane, F. Reimold, M.L. Reinke, S. Wiesen   +15 more
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