J. Linke

Publication List Details

Period

1987 - 9999

Number

81

Co-Authors

Effects of Short Pulse High Heat Fluxes on Carbon Base Plasma Facing Materials for ITER. (9999)

VAN DER Laan, J. G., Klippel, H. Th., Kraaij, G. J., Linke, J.

New experimental results from disruption heat flux simulations in the millisecond range with laser and electron beams are discussed. For a number of graphites, boronated graphites and carbon fiber...

Residual stresses in tungsten under exposures with ITER ELM-like plasma loads. (2009)

Makhlai, V.A., Garkusha, I.E., Malykhin, S.V., Pugachov, A.T., Landman, I., Linke, J., ...

12th Internat.Workshop on Plasma-Facing Materials and Components for Fusion Applications, Jülich, May 11-14, 2009

Failure study of helium-cooled tungsten divertor components tested at DEMO relevant steady-state heat loads. (2009)

Ritz, G., Hirai, T., Norajitra, P., Reiser, J., Giniyatulin, R., Makhankov, A., ...

12th Internat.Workshop on Plasma-Facing Materials and Components for Fusion Applications, Jülich, May 11-14, 2009

Status of plasma facing materials for next step fusion devices. (2009)

Linke, J., Pintsuk, G., Prokhodtseva, A., Rödig, M., Garcia-Rosales, C., Centeno, A., ...

14th Internat.Conf.on Fusion Reactor Materials (ICFRM-14), Sapporo, J, September 7-12, 2009

A tritium diagnostic and trap for JUDITH - first results in disruption simulation experiments with neutron irradiated beryllium during cyclic electron beam testing (2008)

Schmidt, A., Uytdenhouwen, Inge, Kuhnlein, W., Roedig, M., Linke, J., Hirai, T., ...

In the present study, the effect of disruptions on beryllium has been studied. Disruptions are simulated in the electron beam facility JUDITH by high energetic pulses of up to 250 MJ/m2. Under these...

Development and testing of a bulk tungsten tile for the JET divertor (2007)

Hirai, T., Bondarchuk, E., Borovkov, A.I., Koppitz, Th., Linke, J., Mertens, Ph., ...

The ITER-like wall project has been launched to design, manufacture and test all the necessary components in view of their installation in a dedicated shutdown 2008–09. One of the R&D activities in...

Damage to tungsten macro-brush targets under ELM-like heat loads. Experiments vs.numerical simulations. (2007)

Bazylev, B., Janeschitz, G., Landman, I., Pestchanyi, S., Loarte, A., Federici, G., ...

10th European Congress and Exhibition on Advanced Materials and Processes (Euromat 2007), Nürnberg, September 10-13, 2007

ITER transient consequences for material damage. Modelling vs.experiments. (2006)

Bazylev, B., Janeschitz, G., Landman, I., Pestchanyi, S., Loarte, A., Federici, G., ...

11th Internat.Workshop on Plasma-Facing Materials and Components for Fusion Applications, Greifswald, October 10-12, 2006

Modeling of tungsten erosion experiments in JUDITH. (2005)

Bazylev, B.N., Ogorodnikova, O.V., Linke, J.

European Congress on Advanced Materials and Processes (Euromat 2005), Praha, CZ, September 5-8, 2005

Materials for the plasma-facing components of fusion reactors. (2004)

Bolt, H., Barabash, V., Krauss, W., Linke, J., Neu, R., Suzuki, S., ...

11th Internat.Conf.on Fusion Reactor Materials (ICFRM-11), Kyoto, J, December 7-12, 2003

Brittle destruction of carbon based materials. (2004)

Koza, Y., Amouroux, S., Bazylev, B.N., Berthe, E., Kuehnlein, W., Linke, J., ...

Proc.of the 10th Carbon Workshop, Jülich, September 17-19, 2003

Modelling of thermal shock experiments of carbon based materials in JUDITH. (2004)

Ogorodnikova, O.V., Pestchanyi, S., Koza, Y., Linke, J.

16th Internat.Conf.on Plasma Surface Interactions in Controlled Fusion Devices, Portland, Maine, May 24-28, 2004

Arcing at B4C-covered limiters exposed to a SOL-plasma (2003)

Laux,M., Schneider,W., Wienhold,P., Jüttner,B., Huber,A., Balden,M., ...

Plasma sprayed B4C-layers considered as wall coatings for the W7X stellarator have been studied during and after exposure to TEXTOR and after arcing experiments in vacuum. Arcing through the B₄C...

Arcing at B4C-covered limiters exposed to a SOL-plasma (2003)

Laux, M., Schneider, W., Wienhold, P., Jüttner, B., Huber, A., Balden, M., ...

Plasma sprayed B4C-layers considered as wall coatings for the W7X stellarator have been studied during and after exposure to TEXTOR and after arcing experiments in vacuum. Arcing through the B₄C...

Overview of JET results (2003)

Pamela, J., Solano, E. R., Adams, J. M., Agarici, G., Agarici, M., Akhter, H., ...

Scientific and technical activities on JET focus on the issues likely to affect the ITER design and operation. Our understanding of the ITER reference mode of operation, the ELMy H-mode, has...

Status of fabrication development for plasma facing components in the EU. (2003)

Daenner, W., Merola, M., Lorenzetto, P., Peacock, A., Bobin-Vastra, I., Briottet, L., ...

Proc.of the 6th Internat.Symp.on Fusion Nuclear Technology (ISFNT-6), San Diego, Calif., April 7-12, 2002

Plasma facing and high heat flux materials - needs for ITER and beyond (2002)

Bolt,H., Barabash,V., Federici,G., Linke,J., Loarte,A., Roth,J., ...

Plasma-facing materials (PFMs) have to withstand particle and heat loads from the plasma and neutron loads during reactor operation. For ITER knowledge has been accumulated by operation experience...

Development of tungsten coated first wall and high heat flux components for application in ASDEX Upgrade (2002)

Maier,H., Luthin,J., Balden,M., Lindig,S., Linke,J., Rohde,V., ...

In the tokamak experiment ASDEX Upgrade, the investigation of tungsten as a first wall material is an ongoing research project. In a step-by-step strategy, the tungsten covered surface area is...

Plasma facing and high heat flux materials - needs for ITER and beyond (2002)

Bolt, H., Barabash, V., Federici, G., Linke, J., Loarte, A., Roth, J., ...

Plasma-facing materials (PFMs) have to withstand particle and heat loads from the plasma and neutron loads during reactor operation. For ITER knowledge has been accumulated by operation experience...

Development of tungsten coated first wall and high heat flux components for application in ASDEX Upgrade (2002)

Maier, H., Luthin, J., Balden, M., Lindig, S., Linke, J., Rohde, V., ...

In the tokamak experiment ASDEX Upgrade, the investigation of tungsten as a first wall material is an ongoing research project. In a step-by-step strategy, the tungsten covered surface area is...

Nichtmetallische Strukturwerkstoffe im Bereich der Ersten Wand von Fusionsreaktoren. (1987)

Koizlik, K., Dienst, W., Linke, J., Thuemmler, F.

Jahrestagung Kerntechnik, Karlsruhe, 2.-4.Juni 1987 - Fachsitzung 'Materialien fuer Kernfusionsanlagen'