Beryllium migration and evolution of first wall surface composition in the JET ILW configuration

被引:27
作者
Krieger, K. [2 ]
Brezinsek, S. [3 ]
Reinelt, M. [2 ]
Lisgo, S. W. [4 ]
Coenen, J. W. [3 ]
Jachmich, S. [5 ]
Marsen, S. [2 ]
Meigs, A. [6 ]
van Rooij, G. [7 ]
Stamp, M. [6 ]
van Hoey, O. [5 ]
Ivanova, D. [8 ]
Loarer, T. [9 ]
Philipps, V. [3 ]
机构
[1] JET EFDA, Culham Sci Ctr, Abingdon OX14 3DB, Oxon, England
[2] EURATOM, Max Planck Inst Plasmaphys, Garching, Germany
[3] EURATOM, TEC, FZJ, Inst Energieforsch 4, Julich, Germany
[4] ITER Org, FST, F-13067 St Paul Les Durance, France
[5] EURATOM, ERM KMS, Lab F Plasma Phys, Brussels, Belgium
[6] Euratom CCFE Fus Assoc, Culham Sci Ctr, Abingdon OX14 3DB, Oxon, England
[7] EURATOM, Dutch Inst Fundamental Energy Res, Nieuwegein, Netherlands
[8] Assoc EURATOM VR, EES, KTH, Stockholm, Sweden
[9] Assoc EURATOM CEA, CEA Cadarache, St Paul Les Durance, France
基金
英国工程与自然科学研究理事会;
关键词
8;
D O I
10.1016/j.jnucmat.2013.01.042
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Material migration and the resulting evolution of plasma facing surfaces were studied at the beginning of the JET ILW campaign using the singular opportunity of well-defined initial conditions with virgin Be and W wall components. In a sequence of identical Ohmically heated discharges the evolution of wall material sources as well as that of residual impurity sources were studied by spectroscopic detection of suitable emission lines of corresponding neutral atom and singly charged ion species in the visible spectral range. The evolution of divertor surface composition resulting from wall material migration occurred at a similar time scale as previously observed in Be migration experiments in the JET carbon wall configuration. In contrast to these experiments with initial Be evaporation on the carbon main chamber wall, the JET ILW migration experiment is characterised by a continuous Be wall source because the main chamber wall now consists of bulk Be components. The experiment further reveals unexpectedly high Be deposition at W divertor surfaces already during preceding limiter discharges for system commissioning, which has implications for predictive modelling of the expected fuel retention in ITER. (C) 2013 Elsevier B. V. All rights reserved.
引用
收藏
页码:S262 / S266
页数:5
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