Integrated core–SOL–divertor modelling for ITER including impurity: effect of tungsten on fusion performance in H-mode and hybrid scenario

TitleIntegrated core–SOL–divertor modelling for ITER including impurity: effect of tungsten on fusion performance in H-mode and hybrid scenario
Publication TypeJournal Article
Year of Publication2015
AuthorsR. Zagorski, I. Voitsekhovitch, I. Ivanova-Stanik, F. Kochl, daSilva Ares P. Belo, E. Fable, J. Garcia, L. Garzotti, J. Hobirk, G.MD Hogeweij, E. Joffrin, X. Litaudon, A.R Polevoi, G. Telesca, JET Contributors
JournalNuclear Fusion
Volume55
Issue5
Pagination053032
Abstract

The compatibility of two operational constraints—operation above the L–H power threshold and at low power to divertor—is examined for ITER long pulse H-mode and hybrid scenarios in integrated core–scrape off layer (SOL)–divertor modelling including impurities (intrinsic Be, He, W and seeded Ne). The core thermal, particle and momentum transport is simulated with the GLF23 transport model tested in the self-consistent simulations of temperatures, density and toroidal rotation velocity in JET hybrid discharges and extrapolated to ITER. The beneficial effect of toroidal rotation velocity on fusion gain is shown. The sensitivity studies with respect to operational (separatrix and pedestal density, Ne gas puff) and unknown physics (W convective velocity and perpendicular diffusion in SOL as well as W prompt re-deposition) parameters are performed to determine their influence on the operational window and fusion gain.

DOI10.1088/0029-5515/55/5/053032
Division

FP

Department

CPP-HT

PID

88a082ba90add46139f1b78733b8692b

Alternate TitleNucl. Fusion
LabelOA
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