C. Thomser V. Bailescu S. Brezinsek J. W. Coenen H. Greuner T. Hirai J. Linke C. P. Lungu H. Maier G. Matthews Ph. Mertens R. Neu V. Philipps V. Riccardo M. Rubel C. Ruset A. Schmidt I. Uytdenhouwen JET EFDA Contributors
The chosen materials for plasma facing components for the deuterium/tritium phase of ITER are beryllium and tungsten. These materials have already been widely investigated in various devices like ion beam or electron beam tests. However, the operation of this material combination in a large tokamak including plasma wall interaction, material degrad…
PublishedA. Lyssoivan R. Koch J.M. Noterdaeme V. Philipps D. Van Eester et al.
ITER and future superconducting fusion machines need efficient wall conditioning techniques for routine operation in between shots in the presence oi permanent high magnetic field for wall cleaning, surface isotope exchange and to control the in-vessel long term tritium retention. Ion Cyclotron Wall Conditioning (ICWC) based on the ICRF discharge i…
PublishedA. Kreter H. G. Esser S. Brezinsek J. P. Coad A. Kirschner W. Fundamenski V. Philipps R. A. Pitts A. Widdowson
The impact of edge localized modes (ELMs) carrying energies of up to 450 kJ on carbon erosion in the JET inner divertor is assessed by means of time resolved measurements using an in situ quartz microbalance diagnostic. The inner target erosion is strongly nonlinearly dependent on the ELM energy: a single 400 kJ ELM produces the same carbon erosion…
Published