Modelling of beryllium erosion-redeposition on ITER first wall panels

被引：60

作者：

Carpentier, S. ^{[1
]}

Pitts, R. A. ^{[1
]}

Stangeby, P. C. ^{[2
]}

Elder, J. D. ^{[2
]}

Kukushkin, A. S. ^{[1
]}

Lisgo, S. ^{[1
]}

Fundamenski, W. ^{[3
]}

Moulton, D. ^{[3
]}

机构：

[1] ITER Org, CEA Cadarache Ctr, F-13108 St Paul Les Durance, France

[2] Univ Toronto, Inst Aerosp Studies, N York, ON M3H 5T6, Canada

[3] Euratom CCFE Fus Assoc, Culham Sci Ctr, Abingdon OX14 3DB, Oxon, England

来源：

JOURNAL OF NUCLEAR MATERIALS | 2011年 / 415卷 / 01期

关键词：

TRANSPORT;

D O I：

10.1016/j.jnucmat.2010.10.081

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

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 Q(DT) = 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. (C) 2010 Published by Elsevier B.V.

引用

页码：S165 / S169

页数：5

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