Integrated core–SOL–divertor modelling for ITER including impurity: effect of tungsten on fusion performance in H-mode and hybrid scenario. (23rd April 2015)

• Record Type: Journal Article
• Authors: Zagórski, R.; Voitsekhovitch, I.; Ivanova-Stanik, I.; Köchl, F.; Belo, P.; Fable, E.; Garcia, J.; Garzotti, L.; Hobirk, J.; Hogeweij, G.M.D.; Joffrin, E.; Litaudon, X.; Polevoi, A.R.; Telesca, G.
• Other Names: collab.
• Is Part Of: Nuclear fusion. Volume 55:Number 5(2015:May)
• Publication Date: 2015-04-23
• Subjects: ITER -- impurity -- integrated modelling -- core plasma -- edge plasma; 52.55.Fa -- 52.55.Rk -- 52.30.Ex; Nuclear fusion -- Periodicals; 621.48405
• DOI: 10.1088/0029-5515/55/5/053032
• Languages: English
• ISSNs: 0029-5515

Abstract

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.