Results 141 to 150 of about 585 (174)

Research Progress on Rolling Forming of Tungsten Alloy. [PDF]

Materials (Basel)
Cao J, Xia J, Shen X, Song K, Zhou Y, Cui C.   +5 more
europepmc   +1 more source

A molecular dynamics study of the sputtering processes of beryllium species by hydrogenic plasma. [PDF]

Sci Rep
Liptak A, Lawson KD, Hasan MI.
europepmc   +1 more source

Joining and Heat Load Test of Tungsten Divertor

Joining and Heat Load Test of Tungsten Divertor
openaire   +1 more source

Physics basis for the first ITER tungsten divertor

Nuclear Materials and Energy, 2019
On the eve of component procurement, this paper discusses the present physics basis for the first ITER tungsten (W) divertor, beginning with a reminder of the key elements defining the overall design, and outlining relevant aspects of the Research Plan accompanying the new “staged approach” to ITER nuclear operations which fixes the overall divertor ...
X Bonnin, F Escourbiac, H Frerichs
exaly   +4 more sources

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EAST Full Tungsten Divertor Design

Journal of Fusion Energy, 2015
One of the most important research goals of EAST concerns long steady-state high-performance plasma pulse. It is a fusion engineering challenge for divertor to handle steady-state high heat flux form plasma. To accomplish this aim, full tungsten divertor has been designed for EAST to withstand high heat flux which is increasing rapidly.
Lei Cao, Zibo Zhou, Damao Yao
exaly   +2 more sources

Chemically deposited tungsten fibre-reinforced tungsten – The way to a mock-up for divertor applications

Nuclear Materials and Energy, 2016
Published by Elsevier, Amsterdam [u.a.]
J Riesch, J W Coenen, H Gietl
exaly   +6 more sources

The impact of ELM mitigation on tungsten source in the EAST divertor

Nuclear Fusion, 2021
Abstract Divertor tungsten (W) erosion source during edge localized mode (ELM) bursts in EAST is investigated based on optical emission spectroscopy on atomic neutral tungsten line emission at 400.9 nm. Both temporal evolution and total source strength are analyzed and compared in three different ELM mitigation schemes including natural ...
X.H. Chen, F. Ding, L. Wang, Y.W. Sun, R. Ding, S. Brezinsek, Q. Zang, Y.M. Wang, Y.M. Duan, L. Zhang, Z.H. Hu, Q. Zhang, D.W. Ye, Y. Luo, L.Y. Meng, J.B. Liu, Z.S. Yang, G.S. Xu, Y.F. Liang, G.-N. Luo, H.B. Ding, J.S. Hu   +21 more
openaire   +1 more source

The tungsten divertor experiment at ASDEX Upgrade

Plasma Physics and Controlled Fusion, 1996
Tungsten-coated tiles, manufactured by plasma spray on graphite, were mounted in the divertor of the ASDEX Upgrade tokamak and cover almost 90% of the surface facing the plasma in the strike zone. Over 600 plasma discharges have been performed to date, around 300 of which were auxiliary heated with heating powers up to 10 MW. The production of tungsten
Neu, R., Asmussen, K., Krieger, K., Thoma, A., Bosch, H., Deschka, S., Dux, R., Engelhardt, W., GarciaRosales, C., Gruber, O., Herrmann, A., Kallenbach, A., Kaufmann, M., Mertens V, Ryter, F., Rohde V, Roth, J., Sokoll, M., Stabler, A., Suttrop, W., Weinlich, M., Zohm, H., Alexander, M., Becker, G., Behler, K. ; https://orcid.org/0000-0003-2845-8024, Behringer, K., Behrisch, R., Bergmann, A., Bessenrodt-Weberpals, M., Brambilla, M., Brinkschulte, H., Büchl, K., Carlson, A., Chodura, R., Coster, D., Cupido, L., deBlank, H., Hempel, S., Drube, R., Fahrbach, H., Feist, J., Feneberg, W., Fiedler, S., Franzen, P., Fuchs, J., Fussmann, G., Gafert, J., Gehre, O., Gernhardt, J., Haas, G., Herppich, G., Herrmann, W., Hirsch, S., Hoek, M., Hoenen, F., Hofmeister, F., Hohenöcker, H., Jacobi, D., Junker, W., Kardaun, O., Kass, T., Kollotzek, H., Köppendörfer, W., Kurzan, B., Lackner, K., Lang, P., Lang, R., Laux, M., Lengyel, L., Leuterer, F., Manso, M., Maraschek, M., Mast, K., McCarthy, P., Meisel, D., Merkel, R., Müller, H., Münich, M., Murmann, H., Napiontek, B., Neu, G., Neuhauser, J., Niethammer, M., Noterdaeme, J., Pasch, E., Pautasso, G., Peeters, A., Pereverzev, G., Pitcher, C., Poschenrieder, W., Raupp, G., Reinmuller, K., Riedl, R., Rohr, H., Salzmann, H., Sandmann, W., Schilling, H., Schlögl, D., Schneider, H., Schneider, R., Schneider, W., Schramm, G., Schweinzer, J., Scott, B., Seidel, U., Serra, F., Speth, E., Silva, A., Steuer, K., Stober, J., Streibl, B., Treutterer, W., Troppmann, M., Tsois, N., Ulrich, M., Varela, P., Verbeek, H., Verplancke, P., Vollmer, O., Wedler, H., Wenzel, U., Wesner, F., Wolf, R., Wunderlich, R., Zasche, D., Zehetbauer, T., Zehrfeld, H.   +126 more
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Development of tungsten coatings for ITER divertor components

17th IEEE/NPSS Symposium Fusion Engineering (Cat. No.97CH36131), 2002
The EU design of the ITER Divertor Wing envisages the use of tungsten as an armour because of its low sputter rate. To guarantee an adequate armour lifetime a minimum thickness of 5 mm is required. A promising technology to apply W as an armour for extended surfaces is the plasma spray process (PS).
Riccardi, B., Pizzuto, A., Bertamini, L., Vieider, G., et al.   +4 more
openaire   +2 more sources

Engineering Studies on the EAST Tungsten Divertor

IEEE Transactions on Plasma Science, 2014
Experimental advanced superconducting tokamak device is a D-shaped full superconducting tokamak with actively water cooled plasma facing components. To achieve long pulse and high βH-mode plasma, new plasma position and shape are calculated and optimized during the campaign of 2013-2014.
Zibo Zhou, Damao Yao, Lei Cao, Chao Liang, Changle Liu   +4 more
openaire   +1 more source