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1 - Nuclear Sciences and Applications - IAEA

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THE PLASMA BOUNDARY IN JET<br />

<strong>IAEA</strong>-CN-50/A-VII-12<br />

L. DE KOCK, P.E. STOTT, S. CLEMENT 1 , S.K. ERENTS 2 ,<br />

P.J. HARBOUR, M. LAUX 3 , G.M. McCRACKEN 2 , C.S. PITCHER 2 ,<br />

M.F. STAMP, P.C. STANGEBY 4 , D.D.R. SUMMERS, A.J. TAGLE<br />

JET Joint Undertaking,<br />

Abingdon, Oxfordshire,<br />

United Kingdom<br />

Abstract<br />

THE PLASMA BOUNDARY IN JET.<br />

The parameters of the scrape-off layer in JET are presented for the case of the new belt limiters<br />

<strong>and</strong> compared with the earlier case of eight discrete limiters. The scaling with the main plasma<br />

parameters is found to be similar <strong>and</strong> fits a model that correctly describes the dependence on the mean<br />

plasma density but shows a discrepancy with the input power. — The carbon influx relative to the deuterium<br />

influx, derived from spectroscopic measurements, is compared with the influx calculated from<br />

the measured SOL parameters using the physical sputtering plus carbon self-sputtering <strong>and</strong> the charged<br />

particle flux on the belt limiter. Both ratios show a decreasing trend with increasing density, although<br />

a discrepancy at low density remains. — The SOL in neutral beam heated discharges, although not<br />

steady state, shows a behaviour comparable with that in OH iimiter discharges. However, in discharges<br />

with radiofrequency heating the SOL parameters are instantaneously affected by the RF power <strong>and</strong> its<br />

behaviour depends on wall conditions. — Some typical measurements of the SOL parameters in divertor<br />

plasmas are given, showing that in the outer divertor the plasma is hotter than in the inner one (with<br />

correspondingly lower <strong>and</strong> higher density, respectively). The power flow to the outer divertor is higher<br />

than to the inner one, <strong>and</strong> the temperature difference indicates that net currents must flow in the SOL.<br />

1. INTRODUCTION<br />

Edge conditions are important in tokamaks as they determine<br />

impurity production by sputtering at the limiter, the ability of<br />

the scrape-off layer to screen impurities frcm the core of the<br />

discharge <strong>and</strong> the establishment of the H mode of enhanced<br />

confinement in discharges with a magnetic separatrix.<br />

Experimental measurements have been made with Langmuir probes<br />

<strong>and</strong> other diagnostics. Empirical seal ings of the scrape-off<br />

layer parameters in terms of the main discharge parameters have<br />

been established <strong>and</strong> compared with models of the scrape-off<br />

layer. In this paper we review our underst<strong>and</strong>ing of Ohmic <strong>and</strong><br />

additionally heated, discharges in limiter <strong>and</strong> divertor<br />

configurations.<br />

1 Asociaci6n Euratom/CIEMAT, Madrid, Spain.<br />

2 UKAEA Culham Laboratory, Abingdon, Oxfordshire, UK.<br />

3 Central Institute of Electron Physics, Academy of <strong>Sciences</strong>, Berlin, GDR.<br />

4 Institute for Aerospace Studies, University of Toronto, Toronto, Ontario, Canada.<br />

467

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