Results 21 to 30 of about 585 (174)

Impurity control study of radiative tungsten divertor in EAST tokamak

Nuclear Materials and Energy, 2020
EAST was equipped with W-coated divertor plates and dome for the upper divertor, the remaining plasma facing components include the plasma facing components at lower divertor consisted of Carbon materials, at the baffles and main chamber walls consisted ...
YiPing Chen, Dongrui Zhang, Ling Zhang, Liqun Hu, EAST team   +4 more
doaj   +1 more source

Erosion estimates for the divertor and main wall components from STEP

Nuclear Fusion, 2023
The tungsten erosion within Spherical Tokamak for Energy Production (STEP) assuming tungsten main wall and tungsten divertor has been estimated with ERO at the inner and outer divertor, at the inner and outer midplane and at the outboard baffle entrance.
A. Kirschner, S.S. Henderson, S. Brezinsek, J. Romazanov, M. Kovari, C. Baumann, Ch. Linsmeier, E. Flynn, J. Hess, R.T. Osawa, S.L. Newton, D. Moulton, the STEP Team   +12 more
doaj   +1 more source

Tungsten as a Structural Divertor Material

Advances in Science and Technology, 2010
Refractory materials, in particular tungsten base materials are considered as primary candidates for structural high heat load applications in future nuclear fusion power plants. Promising helium-cooled divertor design outlines make use of their high heat conductivity and strength. The upper operating temperature limit is mainly defined by the onset of
Rieth, M., Armstrong, D., Dafferner, B., Heger, S., Hoffmann, A., Hoffmann, M. D., Jäntsch, U., Kübel, C., Materna-Morris, E., Reiser, J., Rohde, M., Scherer, T., Widak, V., Zimmermann, H.   +13 more
openaire   +4 more sources

A solid tungsten divertor for ASDEX Upgrade [PDF]

Physica Scripta, 2011
The conceptual design of a solid tungsten divertor for ASDEX Upgrade (AUG) is presented. The Div-III design is compatible with the existing divertor structure. It re-establishes the energy and heat receiving capability of a graphite divertor and overcomes the limitations of tungsten coatings.
Herrmann, A., Greuner, H., Jaksic, N., Böswirth, B., Maier, H., Neu, R., Vorbrugg, S., ASDEX Upgrade Team   +7 more
openaire   +3 more sources

Use of tungsten material for the ITER divertor

Nuclear Materials and Energy, 2016
AbstractSince the ITER divertor design includes tungsten monoblocks in the vertical target where heat loads are maximal, the design to protect leading edges as well as technology R&D for high performance armor-heat sink joint were necessary to be implemented.
Hirai, T., Panayotis, S., Barabash, V., Amzallag, C., Escourbiac, F., Durocher, A., Merola, M., Linke, J., Loewenhoff, Th., Pintsuk, G., Wirtz, M., Uytdenhouwen, I.   +11 more
openaire   +2 more sources

Tungsten erosion in the outer divertor of JET [PDF]

Journal of Nuclear Materials, 2007
Erosion of tungsten in the outer JET divertor was determined with a set of tungsten coated divertor tiles during the 2001–2004 discharge campaign. The tungsten marker was strongly eroded, with the largest erosion at the outer strike point position, where more than 75% of the initial W disappeared. Strong erosion is also observed at the outer baffle and
Mayer, M., Likonen, J., Coad, J. P., Maier, H., Balden, M., Lindig, S., Vainonen-Ahlgren, E., Philipps, V., JET-EFDA Contributors   +8 more
openaire   +3 more sources

Final Steps to an All Tungsten Divertor Tokamak [PDF]

Journal of Nuclear Materials, 2007
Currently 85% of the plasma facing components of ASDEX Upgrade are tungsten coated. Carbon inux from W PFCs is still observed but a reduction of the C content is found in plasma discharges and a lower C fraction is measured in deposited layers in agreement with modelling.
Neu, R., Bobkov, V., Dux, R., Kallenbach, A., Pütterich, T., Greuner, H., Gruber, O., Herrmann, A., Hopf, C., Krieger, K., Maggi, C. F., Maier, H., Mayer, M., Schmid, K., Suttrop, W., Rohde, V., ASDEX Upgrade Team   +16 more
openaire   +4 more sources

Impurity transport simulation in the peripheral plasma in the large helical device with tungsten closed helical divertor

Nuclear Materials and Energy, 2018
Long pulse plasma discharges in the Large Helical Device have been often interrupted by iron dust emission induced by electric arcing on the surface of the vacuum vessel.
M. Shoji, G. Kawamura, S. Masuzaki, T. Morisaki   +3 more
doaj   +1 more source

R&D of a strain monitoring system for the EAST tungsten divertor

Nuclear Materials and Energy, 2019
The tungsten divertor of the Experimental Advanced Superconducting Tokamak (EAST) device operates at varying temperatures and strong electromagnetic fields during plasma operation. In order to monitor the thermomechanical and electromagnetic responses of
Xingli Wang, Guang-Nan Luo, Wanjing Wang, Qiang Li, Chunyi Xie, Jichao Wang, Qingran Gao, Yuping Xu, Feng Liu, Zhenmao Chen   +9 more
doaj   +1 more source

Tungsten foil laminate for structural divertor applications – Joining of tungsten foils

Journal of Nuclear Materials, 2013
Abstract This paper is the fourth in our series on tungsten laminates. The aim of this paper is to discuss laminate synthesis, meaning the joining of tungsten foils. It is obvious that the properties of the tungsten laminate strongly depend on the combination of (i) interlayer and (ii) joining technology, as this combination defines (i) the condition
Reiser, J., Rieth, M., Möslang, A., Dafferner, B., Hoffmann, J., Mrotzek, T., Hoffmann, A., Armstrong, D. E. J., Yi, X.   +8 more
openaire   +3 more sources