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
Testing of tungsten coatings in JET for the ITER-like wall (2009)
Coad, J. P., Hole, D. E., Kolodinska, E., Likonen, Jari, Lindig, S., Matthews, G. F., ...
Journal of Nuclear Materials. In press
Dynamics of erosion and deposition in tokamaks (2009)
Kreter, A., Brezinsek, S., Coad, J. P., Esser, H. G., Fundamenski, W., Philipps, V., ...
Testing of tungsten coatings in JET for the ITER-like wall (2009)
Coad, J.P., Hole, D.E., Likonen, Jari, Lindig, S., Matthews, G.F., Mayer, M., ...
Journal of Nuclear Materials Vol.390-391, 992-995
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
Testing of tungsten coatings in JET for the ITER-like wall (2009)
Coad, J. P., Hole, D. E., Kolodinska, E., Likonen, J., Lindig, S., Matthews, G. F., ...
Assessment of the flash-lamp photon-cleaning detritiation method tested at JET. (2009)
Bekris, N., Coad, J.P., Widdowson, A., Erbe, A., Ehrmann, J., Kloppe, B.
Journal of Nuclear Materials, 390-391(2009) S.614-17
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
Detritiation of JET tiles by laser cleaning (2008)
Widdowson, A., Coad, J. P., Farcage, D., Hole, D., Likonen, Jari, Renvall, Tommi, ...
Fusion Science and Technology Vol.54 Nr.1, 51 - 54
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
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
Hybrid H-mode scenario with nitrogen seeding and type III ELMs in JET (2008)
Corre, Y., Joffrin, E., Monier-Garbet, P., Andrew, Y., Arnoux, G., Beurskens, M., ...
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
Assessment of the photon-cleaning detritiation method tested at JET. (2008)
Bekris, N., Coad, J.P., Widdowson, A., Erbe, A., Ehrmann, J., Kloppe, B.
18th Internat.Symp.on Plasma Surface Interactions (PSI-18), Toledo, E, May 26-30, 2008
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., ...
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...
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...
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
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., ...
Silicon doping of gallium nitride using ditertiarybutylsilane (2004)
Deatcher, C.J., Liu, C.W., Cheong, M.G., Smith, L.M., Rushworth, S., Widdowson, A., ...
No abstract
Silicon doping of gallium nitride using ditertiarybutylsilane (2004)
Deatcher, C.J., Liu, C., Cheong, M.G., Smith, L.M., Rushworth, S., Widdowson, A., ...
No abstract
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., ...
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., ...