Flux dependence of carbon erosion and implication for ITER J. Roth a, * , A. Kirschner b , W. Bohmeyer f , S. Brezinsek b , A. Cambe d , E. Casarotto b , R. Doerner g , E. Gauthier d , G. Federici h , S. Higashijima e , J. Hogan d , A. Kallenbach a , H. Kubo e , J.M. Layet d , T. Nakano e , V. Philipps b , A. Pospieszczyk b , R. Preuss a , R. Pugno a , R. Ruggie ´ri d , B. Schweer b , G. Sergienko b , M. Stamp c a Max-Planck-Institut fu ¨ r Plasmaphysik, EURATOM Association, Boltzmannstrasse 2, D-85748 Garching, Germany b Institut fu ¨ r Plasmaphysik, Forschungszentrum Ju ¨ lich, EURATOM Association, D-52425 Ju ¨ lich, Germany c EURATOM/UKAEA Fusion Association, Culham Science Center, Abingdon OX14 3DB, UK d Association EURATOM-CEA, CEA Cadarache, F-13108 St. Paul lez Durance, France e Japan Atomic Energy Research Institute, Naka-machi, Maka-gun, Ibaraki-ken 311-0193, Japan f Max-Planck-Institut fu ¨ r Plasmaphysik, EURATOM Association, Mohrenstr. 42, D-10117 Berlin, Germany g Fusion Energy Research Program, University of California San Diego, La Jolla, CA 92093-0417, USA h ITER JWS Garching Co-center, Boltzmannstr. 2, D-85748 Garching, Germany Abstract In a collaboration of eight experiments the dependence of the chemical erosion yield of carbon on the ion flux, U, was established to U 0.54 at high ion fluxes. With this flux dependence a comprehensive description for chemical erosion is available as function of energy, temperature and flux. With this description the erosion and re-deposition of carbon in the ITER divertor can be calculated using the ITER steady-state plasma scenario and the ERO code. The resulting gross and net erosion rates during steady-state phase of discharges are compared to previous estimates using a constant erosion yield of 1.5%. The use of the complete parameter dependence results in an order of magnitude lower erosion, and, accordingly, of the T codeposition inventory. Ó 2004 Elsevier B.V. All rights reserved. PACS: 28.52.Fa; 82.65.i; 52.25.Fi; 52.40.Hf Keywords: Tritium inventory; Co-deposition; Chemical erosion; ERO-code; ITER 1. Introduction The erosion of plasma-facing materials in magneti- cally confined fusion devices is a key issue especially regarding the tritium inventory [1]. Tritium retention is dominated by the inventory retained in deposited layers of eroded material, such that erosion is the starting point of processes leading to build-up of tritium. Erosion due to energetic particle bombardment de- pends on a number of parameters such as particle energy and flux, as well as surface temperature and has seen a remarkable degree of clarification within the last decade [2–5]. Simultaneously, ion beam experiments at energies 0022-3115/$ - see front matter Ó 2004 Elsevier B.V. All rights reserved. doi:10.1016/j.jnucmat.2004.10.115 * Corresponding author. Tel.: +49 89 3299 1387; fax: +49 89 3299 2279. E-mail address: roth@ipp.mpg.de (J. Roth). Journal of Nuclear Materials 337–339 (2005) 970–974 www.elsevier.com/locate/jnucmat