Modelling of beryllium erosion–redeposition on ITER first wall panels

• Published in: Journal of nuclear materials Vol. 415; no. 1; pp. S165 - S169
• Main Authors: Carpentier, S., Pitts, R.A., Stangeby, P.C., Elder, J.D., Kukushkin, A.S., Lisgo, S., Fundamenski, W., Moulton, D.
• Format: Journal Article Conference Proceeding
• Language: English
• Published: Amsterdam Elsevier B.V 01-08-2011; Elsevier
• Subjects: Applied sciences; Controled nuclear fusion plants; Energy; Energy. Thermal use of fuels; Exact sciences and technology; Fission nuclear power plants; Fuels; Installations for energy generation and conversion: thermal and electrical energy; Nuclear fuels; Tokamak; Plasma; Scrape-off layer; Impurity; Tritium; Modeling; Nuclear reactor; Nuclear fusion reactor; Lifetime; Beryllium; Surface plasma interaction; Deposition; Erosion; First wall
• ISSN: 0022-3115; 1873-4820
• DOI: 10.1016/j.jnucmat.2010.10.081

Unlike any current operating tokamak, ITER will operate long pulse, high performance discharges with an almost conformal, shaped and full beryllium first wall. Under such conditions, high Be erosion rates coupled with local redeposition may be a concern for both plasma-facing component lifetime and main chamber fuel retention. Using the LIM-DIVIMP Monte-Carlo impurity transport code, this paper provides an assessment of local tritium co-deposition and net erosion on selected outboard first wall panels located in the region where main chamber fluxes are expected to be high in ITER during QDT=10 reference burning plasmas. In both cases, the estimates are extremely sensitive to the assumptions made with regard to SOL plasma parameters, sputtering yields and co-deposition ratios.