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

被引:37
作者
Borodin, D. [1 ]
Kirschner, A. [1 ]
Carpentier-Chouchana, S. [2 ]
Pitts, R. A. [2 ]
Lisgo, S. [2 ]
Bjoerkas, C. [1 ,3 ]
Stangeby, P. C. [4 ]
Elder, J. D. [4 ]
Galonska, A. [1 ]
Matveev, D. [1 ,5 ]
Philipps, V. [1 ]
Samm, U. [1 ]
机构
[1] Assoc EURATOM FZJ, Forschungszentrum Julich, Inst Energy & Climate Res Plasma Phys, Julich, Germany
[2] ITER Org, F-13115 St Paul Les Durance, France
[3] Univ Helsinki, Dept Phys, EURATOM Tekes, FI-00014 Helsinki, Finland
[4] Univ Toronto, Inst Aerosp Studies, Toronto, ON M3H 5T6, Canada
[5] Univ Ghent, Dept Appl Phys, B-9000 Ghent, Belgium
关键词
D O I
10.1088/0031-8949/2011/T145/014008
中图分类号
O4 [物理学];
学科分类号
0702 ;
摘要
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.
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页数:7
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