ERO code benchmarking of ITER first wall beryllium erosion/re-deposition against LIM predictions

D. Borodin, A. Kirschner, S. Carpentier-Chouchana, R. A. Pitts, S. Lisgo, C. Björkas, P. C. Stangeby, J. D. Elder, A. Galonska, D. Matveev, V. Philipps, U. Samm

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Abstract

Previous studies (Carpentier et al 2011 J. Nucl. Mater. 415 S165-S169) carried out with the LIM code of the ITER first wall (FW) on beryllium (Be) erosion, re-deposition and tritium retention by co-deposition under steady-state burning plasma conditions have shown that, depending on input plasma parameter assumptions and sputtering yields, the erosion lifetime and fuel retention on some parts of the FW can be a serious concern. The importance of the issue is such that a benchmark of this previous work is sought and has been provided by the ERO code (Pitts et al 2011 J. Nucl. Mater. 415 S957-S964) simulations described in this paper. Provided that inputs to the codes are carefully matched, excellent agreement is found between the erosion/deposition profiles from both codes for a given ITER-shaped FW panel. Issues regarding the difficult problem of the correct treatment of Be sputtering are discussed in relation to the simulations. The possible influence of intrinsic Be impurity is investigated.

Original languageEnglish
Article number014008
JournalPhysica Scripta
VolumeT145
DOIs
StatePublished - 2011
Externally publishedYes
Event13th International Workshop on Plasma-Facing Materials and Components for Fusion Applications, PFMC-13 and 1st International Conference on Fusion Energy Materials Science, FEMaS-1 - Rosenheim, Germany
Duration: 9 May 201113 May 2011

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