Plasma-surface interaction in the Be/W environment: Conclusions drawn from the JET-ILW for ITER

被引：167

作者：

Brezinsek, S. ^{[1
,2
]}

机构：

[1] JET EFDA, Culham Sci Ctr, Abingdon OX14 3DB, Oxon, England

[2] Forschungszentrum Julich, Inst Energie & Klimaforsch Plasmaphys, D-52425 Julich, Germany

来源：

JOURNAL OF NUCLEAR MATERIALS | 2015年 / 463卷

基金：

欧盟地平线“2020”;

关键词：

FUEL RETENTION; INNER WALL; EROSION; BERYLLIUM; MIGRATION; OPERATION; DENSITY; CARBON; POWER;

D O I：

10.1016/j.jnucmat.2014.12.007

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

The JET ITER-Like Wall experiment (JET-ILW) provides an ideal test bed to investigate plasma-surface interaction (PSI) and plasma operation with the ITER plasma-facing material selection employing beryllium in the main chamber and tungsten in the divertor. The main PSI processes: material erosion and migration, (b) fuel recycling and retention, (c) impurity concentration and radiation have bel en studied and compared between JET-C and JET-ILW. The current physics understanding of these key processes in the JET-ILW revealed that both interpretation of previously obtained carbon results (JET-C) and predictions to ITER need to be revisited. The impact of the first-wall material on the plasma was underestimated. Main observations are: (a) low primary erosion source in H-mode plasmas and reduction of the material migration from the main chamber to the divertor (factor 7) as well as within the divertor from plasma-facing to remote areas (factor 30 - 50). The energetic threshold for beryllium sputtering minimises the primary erosion source and inhibits multi-step re-erosion in the divertor. The physical sputtering yield of tungsten is low as 10(-5) and determined by beryllium ions. (b) Reduction of the long-term fuel retention (factor 10 - 20) in JET-ILW with respect to JET-C. The remaining retention is caused by implantation and co-deposition with beryllium and residual impurities. Outgassing has gained importance and impacts on the recycling properties of beryllium and tungsten. (c) The low effective plasma charge (Z(eff) = 1.2) and low radiation capability of beryllium reveal the bare deuterium plasma physics. Moderate nitrogen seeding, reaching Z(eff) = 1.6, restores in particular the confinement and the L-H threshold behaviour. ITER-compatible divertor conditions with stable semi-detachment were obtained owing to a higher density limit with ILW. Overall JET demonstrated successful plasma operation in the Be/W material combination and confirms its advantageous PSI behaviour and gives strong support to the ITER material selection. (C) 2014 The Authors. Published by Elsevier B.V. This is an open access article under the CC BY-NC-ND license.

引用

页码：11 / 21

页数：11

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