Tungsten divertor erosion in all metal devices: Lessons from the ITER like wall of JET
Authors:
- G.J. van RooijGRG.J. van Rooij
- J.W. CoenenJ.W. Coenen
- L. Aho-MantilaLAL. Aho-Mantila
- S. BrezinsekSBS. Brezinsek
- M. GrothMGM. Groth
- R. NeuRNR. Neu
- 1 July 2013
- journal article
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 438, S42-S47
Abstract
No abstract availableFunding Information
- Foundation for Fundamental Research on Matter
- H2020 Euratom
This publication has 10 references indexed in Scilit:
- Integration of a radiative divertor for heat load control into JET high triangularity ELMy H-mode plasmasNuclear Fusion, 2012
- Quantification of tungsten sputtering at W/C twin limiters in TEXTOR with the aid of local WF6injectionPhysica Scripta, 2011
- Enhancement of JET’s mirror-link near-ultraviolet to near-infrared divertor spectroscopy systemReview of Scientific Instruments, 2010
- Determination of rate coefficients for fusion-relevant atoms and molecules by modelling and measurement in the boundary layer of TEXTORJournal of Physics B: Atomic, Molecular and Optical Physics, 2010
- Plasma-wall interaction and plasma behaviour in the non-boronised all tungsten ASDEX UpgradeJournal of Nuclear Materials, 2009
- Characterization of the deuterium recycling flux in front of a graphite surface in the TEXTOR tokamakPlasma Physics and Controlled Fusion, 2005
- Divertor impurity sources; effects of hot surfaces and thin films on impurity productionJournal of Nuclear Materials, 2005
- Reduction of divertor heat load in JET ELMy H-modes using impurity seeding techniquesNuclear Fusion, 2004
- Tungsten as target material in fusion devicesNuclear Fusion, 1996
- Spectroscopic determination of impurity influx from localized surfacesPlasma Physics and Controlled Fusion, 1989