Results 31 to 40 of about 1,452 (264)

Numerical study of divertor detachment in the MAST-U tokamak [PDF]

, 2022
Divertor detachment is a promising method to reduce heat loading and erosion in tokamak devices or even in future magnetic fusion reactors. In this thesis, two detachment regimes (increasing upstream density and seeding impurity) leading to the decrease ...
Zhou, Yulin
core  

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.
W7-X Team, Feng, Y., Jakubowski, M., König, R., Krychowiak, M., Otte, M., Reimold, F., Reiter, D., Schmitz, O., Zhang, D., Beidler, C. D., Biedermann, C., Bozhenkov, S., Brunner, K. J., Dinklage, A., Drewelow, P., Effenberg, F., Endler, M., Fuchert, G., Gao, Y., Geiger, J., Hammond, K. C., Helander, P., Killer, C., Knauer, J., Kremeyer, T., Pasch, E., Rudischhauser, L., Schlisio, G., Sunn Pedersen, T., Wenzel, U., Winters, V., Gantenbein, Gerd, Huber, Martina, Illy, Stefan, Jelonnek, John, Kobarg, Thorsten, Lang, Rouven, Leonhardt, Wolfgang, Mellein, Daniel, Papenfuß, Daniel, Scherer, Theo, Thumm, Manfred, Wadle, Simone, Weggen, Jörg   +44 more
openaire   +5 more sources

Divertor detachment during pure helium plasmas in JET

, 2003
A campaign of pure helium discharges in the JET tokamak equipped with the MarkIIGB divertor has been performed. This paper describes some of the experimental observations of divertor detachment obtained in L-mode density ramp He discharges and presents a
Reiter, D., Tsitrone, E., Wischmeier, M., Pitts, R. A., Bonnin, X., Eich, T., Matthews, G. F., Coster, D., Jachmich, S., Loarte, A., Kukushkin, A., Ingesson, C., Huber, A., Rapp, J.   +13 more
core   +3 more sources

Physics of plasma transport and divertor detachment in novel divertor configurations [PDF]

, 2023
In this dissertation, we investigate two proposed features aimed at improving the performance of the divertor exhaust system in tokamak nuclear fusion devices.
Masline, Rebecca Lee
core  

Argon–seeded detachment during ELM control by RMPs in KSTAR

Nuclear Fusion, 2023
In this study, we demonstrate argon-seeded discharges that exhibited a detached divertor during the full suppression and mitigation of edge-localized modes (ELMs) by an International Thermonuclear Experimental Reactor-like, three-row resonant magnetic ...
H. Shin, J. Hwang, Y. Han, G. Shin, H. Lee, K.-B. Chai, Wonho Choe   +6 more
doaj   +1 more source

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
doaj   +1 more source

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
doaj   +1 more source

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
doaj   +1 more source

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

Micropillar‐Engineered Hybrid Adhesive Patch for Surface‐Conformable and Directional Adhesion

Advanced Materials Technologies, EarlyView.
This work presents a surface‐conformable hybrid adhesive integrating height‐optimized hexagonal micropillars with open‐rectangular cuts. The micropillars enhance rough‐surface contact and microscale crack arrest, while the cuts guide and reverse interfacial cracks for strong and directional adhesion. The multiscale architecture achieves robust pull‐off
Seongjin Park, Dong Kwan Kang, Haejin Bae, Ho‐Sup Jung, Hoon Eui Jeong   +4 more
wiley   +1 more source