Analysis of fuel retention in plasma-facing components from controlled fusion devices (2009)
Rubel, M., Coad, J. P., Likonen, Jari, Philipps, V., JET-EFDA Contributors
Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms Vol.267 Nr.4, 711 - 717
Post-mortem measurements of fuel retention at JET with MKII-SRP divertor (2009)
Likonen, Jari, Coad, J. P., Hole, D. E., Koivuranta, Seppo, Renvall, T., Rubel, M., ...
Journal of Nuclear Materials. In press
Deposition of 13C tracer at the JET MKII-HD divertor (2009)
Likonen, Jari, Hakola, Antti, Coad, J.P., Widdowson, A., Strachan, J., Koivuranta, Seppo, ...
12th International Workshop on Plasma Facing Materials and Components for Fusion Applications, Jülich, Germany, May 11-14, 2009
An overview of recent erosion - deposition studies at JET (2009)
Widdowson, A., Coad, J.P., Esser, H.G., Hole, D.E., Kreter, A., Likonen, Jari, ...
12th International Workshop on Plasma Facing Materials and Components for Fusion Applications, Jülich, Germany, May 11-14, 2009
Surface structure and composition of first mirrors tested in JET for ITER (2009)
Rubel, M., Uytdenhouwen, I., Coad, J.P., Temmerman, G.de, Hole, D., Likonen, Jari, ...
12th International Workshop on Plasma Facing Materials and Components for Fusion Applications, Jülich, Germany, May 11-14, 2009
A concise overview is given on materials applied in fusion technology. The influence of plasma operation on the behaviour of reactor components and diagnostic systems is discussed with emphasis on...
INSTITUTE OF PHYSICS PUBLISHING PLASMA PHYSICS AND CONTROLLED FUSION (2008)
G Counsell, P Coad, C Grisola, C Hopf, W Jacob, A Kirschner, ...
Tritium retention in next step devices and the
Structural investigation of re-deposited layers in JET (2008)
Likonen, Jari, Vainonen-Ahlgren, E., Khriachtchev, L., Coad, J. P., Rubel, M., Renvall, T., ...
Journal of Nuclear Materials. In press
Modelling of Carbon Migration during JET 13C Injection Experiments (2008)
Strachan, J.D., Likonen, Jari, Coad, P., Rubel, M., Widdowson, A., Airila, Markus Et Al.
Nuclear Fusion Nr.48, 105002
Structural investigation of re-deposited layers in JET (2008)
Likonen, Jari, Vainonen-Ahlgren, Elizaveta, Khriachtchev, L., Coad, J., Rubel, M., Renvall, Tommi, ...
Journal of Nuclear Materials Nr.377, 486-491
Modelling of carbon migration during JET 13C injection experiments (2008)
Strachan, J. D., Likonen, J., Coad, P., Rubel, M., Widdowson, A., Airila, M., ...
Post-mortem measurements on fuel retention at JET with MKII-SRP divertor (2008)
Likonen, Jari, Coad, J.P., Vainonen-Ahlgren, E., Hole, D.E., Rubel, M., Renvall, Tommi, ...
PSI18 - 18th International Conference on Plasma Surface Interactions in Controlled Fusion Devices, Toledo, Spain, May 26-30 2008
Hirai, T., Linke, J., Rubel, M., Coad, J. P., Likonen, Jari, Lungu, C. P., ...
Fusion Engineering and Design Vol.83 Nr.7 - 9, 1072 - 1076
Modelling of carbon migration during JET 13C injection experiments (2008)
Strachan, J. D., Likonen, Jari, Coad, P., Rubel, M., Widdowson, A., Airila, M., ...
Nuclear Fusion Vol.48 Nr.10, art. no. 105002
R&D on full tungsten divertor and beryllium wall for JET ITER-like wall project (2007)
Hirai, T., Maier, H., Rubel, M., Mertens, Ph., Neu, R., Gauthier, E., ...
The ITER reference materials have been tested separately in tokamaks, plasma simulators, ion beams and high heat flux test beds. In order to perform a fully integrated material test JET has launched...
Tungsten and beryllium armour development for the JET ITER-like wall project (2007)
Maier, H., Hirai, T., Rubel, M., Mertens, Ph., Greuner, H., Hopf, Ch., ...
For the ITER-like wall project at JET, the present main chamber CFC tiles will be exchanged with Be tiles and in parallel a fully tungsten-clad divertor will be prepared. Three R&D programmes were...
Overview of the ITER-like Wall Project (2007)
Matthews, G., Edwards, P., Hirai, T., Kear, M., Lioure, A., Lomas, P., ...
Tungsten and Beryllium Armour Development for the JET ITER-like Wall Project (2007)
Maier, H., Hirai, T., Rubel, M., Neu, R., Mertens, P., Greuner, H., ...
Gas Balance and Fuel Retention in Fusion Devices (2007)
Loarer, T., Brosset, C., Bucalossi, J., Coad, P., Esser, G., Hogan, J., ...
Tungsten and Beryllium Armour Development for the JET ITER-like Wall Project (2007)
Maier, H., Hirai, T., Rubel, M., Neu, R., Mertens, P., Greuner, H., ...
R&D on full tungsten divertor and beryllium wall for JET ITER-like wall project (2007)
Hirai, T., Maier, H., Rubel, M., Mertens, Ph., Neu, R., Gauthier, E., ...
Fusion Engineering and Design Vol.82 Nr.15 - 24, 1839 - 1845
Erosion and deposition in the JET MkII-SRP divertor (2007)
Coad, J. P., Andrew, P., Erents, S. K., Hole, D. E., Likonen, J., Mayer, M., ...
R&D on tungsten plasma facing components for the JET ITER-like wall project (2007)
Piazza, G., Matthews, G. F., Pamela, J., Altmann, H., Coad, J. P., Hirai, T., ...
Gas balance and fuel retention in fusion devices (2007)
Loarer, T., Brosset, C., Bucalossi, J., Coad, P., Esser, G., Hogan, J., ...
R&D on full tungsten divertor and beryllium wall for JET ITER-like Wall Project (2007)
Hirai, T., Maier, H., Rubel, M., Mertens, P., Neu, R., Gauthier, E., ...
Carbon migration during JET 13C experiments (2007)
Strachan, J.D., Coad, P., Corrigan, G., Spence, J., Matthews, G.F., Airila, M., ...
Litnovsky, A., Wienhold, P., Philipps, V., Sergienko, G., Schmitz, O., Kirschner, A., ...
Metal mirrors will be implemented in about half of the ITER diagnostics. Mirrors in ITER will have to withstand radiation loads, erosion by charge-exchange neutrals, deposition of impurities,...
Erosion and deposition in the JET MkII-SRP divertor (2007)
Coad, J. P., Andrew, P., Erents, S. K., Hole, D. E., Likonen, J., Mayer, M., ...
Carbon-13 labelled methane was injected into the outer divertor during a series of H-mode discharges on the last day of operations with the JET MkII-SRP divertor. Tiles from around the vessel were...
Tungsten and beryllium armour development for the JET ITER-like wall project (2007)
MAIER, H, HIRAI, T, RUBEL, M, NEU, R, MERTENS, P, GREUNER, H, ...
Gas balance and fuel retention in fusion devices (2007)
T. Loarer, C. Brosset, J. Bucalossi, P. Coad, G. Esser, J. Hogan, ...
The evaluation of hydrogenic retention in present tokamaks is of crucial importance to estimate the expected tritium (T) vessel inventory in ITER, limited from safety considerations to 350 g. In the...
Sergienko, G., Bazylev, B., Hirai, T., Huber, A., Kreter, A., Mertens, Ph., ...
Physica Scripta, T128(2007) S.81-86
Sergienko, G., Bazylev, B., Hirai, T., Huber, A., Kreter, A., Mertens, Ph., ...
11th Internat.Workshop on Plasma-Facing Materials and Components for Fusion Applications, Greifswald, October 10-12, 2006
Erosion of a tungsten limiter under high heat flux in TEXTOR . (2007)
Sergienko, G., Bazylev, B., Huber, A., Kreter, A., Litnovsky, A., Rubel, M., ...
Journal of Nuclear Materials, 363-365(2007) S.96-100
Efficacy of photon cleaning of JET divertor tiles. (2007)
Widdowson, A., Coad, J.P., Bekris, N., Counsell, G., Forrest, M.J., Gibson, K.J., ...
Journal of Nuclear Materials, 363-365(2007) S.341-45
Grisolia, C., Counsell, G., Dinescu, G., Semerok, A., Bekris, N., Coad, P., ...
Fusion Engineering and Design, 82(2007) S.2390-98
R&D on full tungsten divertor and beryllium wall for JET ITER-like wall project (2007)
Hirai, T., Maier, H., Rubel, M., Mertens, Ph., Neu, R., Gauthier, E., ...
Material Erosion and Redeposition during the JET MkIIGB-SRP Divertor Campaign (2006)
Kirschner, A., Philipps, V., Balden, M., Bonnin, X., Brezinsek, S., Coad, J., ...
Gas Balance and Fuel Retention in Fusion Devices (2006)
Loarer, T., Brosset, C., Bucalossi, J., Coad, P., Esser, G., Hogan, J., ...
Tungsten and Beryllium Armour Development for the JET ITER-like Wall Project (2006)
Maier, H., Hirai, T., Rubel, M., Neu, R., Mertens, P., Greuner, H., ...
Overview of the ITER-like Wall Project. Invited paper (2006)
Matthews, G., Edwards, P., Hirai, T., Kear, M., Lioure, A., Lomas, P., ...
Erosion and Deposition in the JET Mk IISRP Divertor (2006)
Coad, J.P., Andrew, P., Erents, S.K., Hole, D.E., Likonen, J., Mayer, M., ...
Carbon Migration during JET 13C Injection Experiments (2006)
Strachan, J.D., Coad, J.P., Corrigan, G., Spence, J., Matthews, G.F., Likonen, J., ...
Effective laser–induced removal of co–deposited layers from plasma–facing components (2006)
P. Gasior, A. Czarnecka, P. Parys, M. Rosinski, J. Wolowski, J. Hoffman, ...
in a tokamak
JET contributions to ITER technology issues. (2006)
Grisolia, C., Rosanvallon, S., Coad, P., Bekris, N., Braet, J., Brennan, D., ...
Fusion Engineering and Design, 81(2006) S.149-54
Diagnostics for studying deposition and erosion processes in JET (2005)
Coad, J. P., Likonen, J., Mayer, M., Neill, G., Philipps, V., ...
Exposure of metal mirrors in the scrape-off layer of TEXTOR (2005)
Wienhold, P., Litnovski, A., Phillips, V., Schweer, B., Sergienko, G., Oelhafen, P., ...
Deuterium retention in Tore Supra long discharges (2005)
Tsitrone, E., Brosset, C., Bucalossi, J., Pegourie, B., Loarer, T., Roubin, P., ...
Material erosion and migration in tokamaks. Invited paper (2005)
Pitts, R. A., Coad, J. P., Coster, D. P., Federici, G., Fundamenski, W., Horacek, J., ...
Material erosion and migration in tokamaks (2005)
Pitts, R. A., Coad, J. P., Coster, D. P., Federici, G., Fundamenski, W., Horacek, J., ...
The issue of first wall and divertor target lifetime represents one of the greatest challenges facing the successful demonstration of integrated tokamak burning plasma operation, even in the case of...
R A Pitts, J P Coad, D P Coster, G Federici, W Fundamenski, J Horacek, ...
The issue of first wall and divertor target lifetime represents one of the greatest challenges facing the successful demonstration of integrated tokamak burning plasma operation, even in the case of...
Characterization of laser-irradiated (2005)
P G ˛asior, J Badziak, A Czarnecka, P Parys, J Wołowski, M Rosiński, ...
co-deposited layers on plasma facing components from a tokamak
Coad, J.P., Rubel, M., Bekris, N., Brennan, D., Hole, D., Likonen, J., ...
7th Internat.Conf.on Tritium Science and Technology, Baden-Baden, September 12-17, 2004
Coad, J.P., Rubel, M., Bekris, N., Brennan, D., Hole, D., Likonen, J., ...
Fusion Science and Technology, 48(2005) S.551-56
Tritium related studies within JET fusion technology work programme. (2005)
Rosanvallon, S., Bekris, N., Braet, J., Coad, P., Counsel, G., Cristescu, I., ...
Fusion Science and Technology, 48(2005) S.268-273
Voitsenya, V.S., Gil, Ch., Konovalov, V.G., Litnovsky, A., Lipa, M., Rubel, M., ...
First mirrors will be the plasma facing components of optical diagnostic systems in ITER. Mirror surfaces will undergo modification caused by erosion and re-deposition processes [1,2]. As a...
Voitsenya, V.S., Gil, Ch., Konovalov, V.G., Litnovsky, A., Lipa, M., Rubel, M., ...
First mirrors will be the plasma facing components of optical diagnostic systems in ITER. Mirror surfaces will undergo modification caused by erosion and re-deposition processes [1,2]. As a...
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...
B4C-limiter experiments at TEXTOR (2003)
Pospieszczyk, A., Schweer, B., Philipps, V., Huber, A., Sergienko, G., Samm, U., ...
In the TEXTOR tokamak the five top and five bottom poloidal carbon limiter blocks have been replaced by inertially cooled copper blocks coated with a 170 μm VPS-B4C layer. Similar limiter blocks...
Short and long range transport of materials eroded from wall components in fusion devices (2003)
Wienhold, P., Philipps, V., Kirschner, A., Huber, A., Von Seggern, J., Esser, H. G., ...
Carbon sources and the sinks have been quantified in TEXTOR and are discussed in terms of short and long range transport. The major source (22 g/h) is the graphite belt limiter, but part (10 g/h) of...
Rubel, M., Wienhold, P., Hildebrandt, D.
Application of ion beam analysis techniques in the studies of material transport and fuel inventory in the controlled fusion devices is exemplified. Enhanced proton scattering on the carbon isotopes...
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...
Beryllium and carbon films in JET following D-T operation. (2003)
Rubel, M., Coad, J.P., Bekris, N., Erents, S.K., Hole, D., Matthews, G.F., ...
Proc. of the 15th Internat.Conf.on Plasma Surface Interactions in Controlled Fusion Devices (PSI-15), Gifu, J, May 27-31, 2002
Overview of fuel retention in composite and tungsten limiters (2002)
Rubel, M., Philipps, V., Pospieszczyk, A., Tanabe, T., Kötterl, S.
A number of materials, in a form of limiters, have been tested at the TEXTOR tokamak as candidates for plasma facing components in future devices. The results for fuel distribution and content in...
Rubel, M., Cecconello, M., Malmberg, J. A., Sergienko, G., Biel, W., Drake, J. R., ...
This version is available at the following URL: http://dx.doi.org/10.1088/0029-5515/41/8/312
Carbon Transport in TEXTOR-94 Aspects of Long Term Operation (2000)
Wienhold, P., Hildebrandt, D., Kirschner, A., Mayer, M., Rubel, M.
Comparison of tokamak behaviour with tungsten and low-Z plasma facing materials (2000)
Philipps, V., Neu, R., Rapp, J., Samm, U., Tokar, A. D., Tanabe, T., ...
This version is available at the following Publisher URL: http://dx.doi.org/10.1088/0741-3335/42/12B/322
Properties of thin a-C/Si:H coatings applied to TEXTOR (1995)
Vonseggern, J., Winter, J., Grobusch, L., Esser, H. G., Vietzke, E., Weschenfelder, F., ...
Thin, hydrogenated silicon and carbon containing films have been deposited by the siliconization procedure on targets made from some metal alloys, pure metals, graphite and Si single crystal. The...
Properties of Thin a-C/Si-H Coatings Applied to Textor (1995)
Vonseggern, J., Winter, J., Grobusch, L., Esser, H. G., Vietzke, E., Weschenfelder, F., ...
Thin, hydrogenated silicon and carbon containing films have been deposited by the siliconization procedure on targets made from some metal alloys, pure metals, graphite and Si single crystal. The...
Exposition von Molybdän-Spiegeln am Plasmarand von TEXTOR
Wienhold, P., Litnovski, A., Phillips, V., Schweer, B., Sergienko, G., Oelhafen, P., ...
Exposure of Molybdenum Mirrors in the Scrape-off Layer of TEXTOR
Wienhold, P., Litnovski, A., Phillips, V., Schweer, B., Sergienko, G., Oelhafen, P., ...
Tritium retention in next step devices and the requirements for mitigation and removal techniques
Counsell, G., Coad, P., Grisolia, C., Hopf, C., Jacob, W., Kirschner, A., ...
Erosion and deposition in the JET Mk IISRP divertor
Coad, J., Andrew, P., Hole, D., Likonen, J., Mayer, M., Rubel, M., ...
R&D on full tungsten divertor and beryllium wall for JET ITER-like Wall Project
Hirai, T., Maier, H., Rubel, M., Mertens, P., Neu, R., Gauthier, E., ...
Overview of the ITER-like Wall Project
Matthews, G., Edwards, P., Hirai, T., Kear, M., Lioure, A., Lomas, P., ...
Tritium retention in next step devices and the requirements for mitigation and removal techniques
Counsell, G., Coad, P., Grisolia, C., Hopf, C., Jacob, W., Kirschner, A., ...
Progress with Tritium Removal and Mitigation 2006-7
Counsell, G., Coad, P., Ferreira, J. A., Rubel, M., Tabares, F. L., Widdowson, A., ...
Tritium Intentory in ITER: Laboratory data and extrapolation from tokamaks
Loarer, T., Roth, J., Brezinsek, S., Kirschner, A., Mayer, M., Neu, R., ...