5 – ASDEX Upgrade

Experiments in the midsized tokamak ASDEX Upgrade (AUG) aim at improving the physics base for ITER and DEMO to prepare operation and aid the design. Being equipped with all tungsten plasma facing components ASDEX Upgrade could acquire important results concerning the fuel retention, tungsten sources and transport important for the operation of all metal devices. The availability of powerful heating systems as well as a comprehensive set of diagnostics allowed pushing the physics understanding in several areas such as pedestal and H-Mode physics, power exhaust and magneto hydro-dynamics (MHD) and development of integrated operational scenarios. Over the next 2 years the capabilities of the heating and current drive systems will be further improved, finally making available about 34 MW of auxiliary heating power. Additionally, existing diagnostic systems will be upgraded and new ones will be installed in order to provide even better insight into the physics of advanced and high power exhaust scenarios.

[1]  K. Krieger,et al.  Nitrogen retention in ASDEX Upgrade , 2015 .

[2]  H. Zohm,et al.  Recent ASDEX Upgrade research in support of ITER and DEMO , 2015 .

[3]  P T Lang,et al.  First observation of edge localized modes mitigation with resonant and nonresonant magnetic perturbations in ASDEX Upgrade. , 2011, Physical review letters.

[4]  L. Giannone,et al.  Partial detachment of high power discharges in ASDEX Upgrade , 2015 .

[5]  S. Fietz,et al.  Influence of externally applied magnetic perturbations on neoclassical tearing modes at ASDEX Upgrade , 2014 .

[6]  L. Giannone,et al.  ICRF antenna-plasma interactions and its influence on W sputtering in ASDEX upgrade , 2011 .

[7]  W. Suttrop,et al.  Survey of the H-mode power threshold and transition physics studies in ASDEX Upgrade , 2013 .

[8]  Jet Efda Contributors,et al.  Observations on the W-transport in the core plasma of JET and ASDEX Upgrade , 2013 .

[9]  R. Neu,et al.  Determination of the tungsten divertor retention at ASDEX upgrade using a sublimation probe , 2002 .

[10]  F. Ryter,et al.  Multi-view fast-ion D-alpha spectroscopy diagnostic at ASDEX Upgrade. , 2013, The Review of scientific instruments.

[11]  W. Treutterer,et al.  Divertor power load feedback with nitrogen seeding in ASDEX Upgrade , 2010 .

[12]  J. Stober,et al.  Resolving the bulk ion region of millimeter-wave collective Thomson scattering spectra at ASDEX Upgrade. , 2014, The Review of scientific instruments.

[13]  R. Neu,et al.  Dynamic and static deuterium inventory in ASDEX Upgrade with tungsten first wall , 2009 .

[14]  R. Dux,et al.  Main chamber sources and edge transport of tungsten in H-mode plasmas at ASDEX Upgrade , 2011 .

[15]  R. Neu,et al.  Modelling of measured tungsten spectra from ASDEX Upgrade and predictions for ITER , 2008 .

[16]  R. Neu,et al.  Conclusions about the use of tungsten in the divertor of ASDEX Upgrade , 1999 .

[17]  C. Linsmeier,et al.  Interaction of nitrogen plasmas with tungsten , 2010 .

[18]  L. Giannone,et al.  Mitigation of edge localised modes with magnetic perturbations in ASDEX Upgrade , 2013 .

[19]  Tomonori Takizuka,et al.  Power requirement for accessing the H-mode in ITER , 2008 .

[20]  R. Dux,et al.  The implications of high-Z first-wall materials on noble gas wall recycling , 2007 .

[21]  Scaling of the divertor power spreading (S-factor) in open and closed divertor operation in JET and ASDEX Upgrade , 2015 .

[22]  R. Neu,et al.  Z dependence of the core impurity transport in ASDEX Upgrade H mode discharges , 1999 .

[23]  L. Giannone,et al.  Assessment of compatibility of ICRF antenna operation with full W wall in ASDEX Upgrade , 2010 .

[24]  T. Lunt,et al.  Impact of magnetic perturbation coils on the edge radial electric field and turbulence in ASDEX Upgrade , 2015 .

[25]  R. Neu,et al.  EMC3-Eirene simulations of the spatial dependence of the tungsten divertor retention in ASDEX Upgrade , 2011 .

[26]  Joachim Roth,et al.  Recent analysis of key plasma wall interactions issues for ITER , 2009 .

[27]  K. Behler,et al.  Real-time feedback control of the plasma density profile on ASDEX Upgrade , 2011 .

[28]  R. Neu,et al.  New results from the tungsten programme at ASDEX Upgrade , 2003 .

[29]  F. Ryter,et al.  L- to H-mode transitions at low density in ASDEX Upgrade , 2011 .

[30]  T. Lunt,et al.  Fast-ion redistribution and loss due to edge perturbations in the ASDEX Upgrade, DIII-D and KSTAR tokamaks , 2013 .

[31]  R. Neu,et al.  Deuterium inventory in the full-tungsten divertor of ASDEX Upgrade , 2010 .

[32]  Gerhard Raupp,et al.  ASDEX Upgrade Discharge Control System – A real-time plasma control framework , 2014 .

[33]  T. Lunt,et al.  Overview on plasma operation with a full tungsten wall in ASDEX Upgrade , 2013 .

[34]  E. Joffrin,et al.  Characterisation of plasma breakdown at JET with a carbon and ITER-like wall , 2013 .

[35]  T. L. Rhodes,et al.  Suppression of large edge localized modes with edge resonant magnetic fields in high confinement DIII-D plasmas , 2005 .

[36]  M. Balden,et al.  Deuterium retention in bulk tungsten exposed to the outer divertor plasma of ASDEX Upgrade , 2011 .

[37]  Y. R. Martin,et al.  Plasma wall interaction and its implication in an all tungsten divertor tokamak , 2007 .

[38]  L. Barrera Orte,et al.  Experimental evidence for the key role of the ion heat channel in the physics of the L–H transition , 2014 .

[39]  R. Neu,et al.  Induced tungsten melting events in the divertor of ASDEX Upgrade and their influence on plasma performance , 2011 .

[40]  G. Pautasso,et al.  Assimilation of impurities during massive gas injection in ASDEX Upgrade , 2015 .

[41]  V. Toigo,et al.  Design of in-vessel saddle coils for MHD control in ASDEX Upgrade , 2009 .

[42]  Patrick J. McCarthy,et al.  Measurement of neoclassically predicted edge current density at ASDEX Upgrade , 2012 .

[43]  D. Carralero,et al.  Far scrape-off layer particle and heat fluxes in high density – High power scenarios , 2015 .

[44]  G. V. Pereverzev,et al.  TORBEAM, a beam tracing code for electron-cyclotron waves in tokamak plasmas , 2001 .

[45]  R. Neu,et al.  Tokamak operation with high-Z plasma facing components , 2005 .

[46]  A. Mlynek,et al.  Studies of edge localized mode mitigation with new active in-vessel saddle coils in ASDEX Upgrade , 2011 .

[47]  A. Kallenbach,et al.  Long term project in ASDEX upgrade: Implementation of ferritic steel as in vessel wall , 2015 .

[48]  L. Giannone,et al.  ICRF operation with improved antennas in ASDEX Upgrade with W wall , 2013 .

[49]  Frank Jenko,et al.  Electron temperature gradient driven turbulence , 1999 .

[50]  J. Stober,et al.  Ten years of W programme in ASDEX Upgrade—challenges and conclusions , 2009 .

[51]  R. Neu,et al.  Tungsten: an option for divertor and main chamber plasma facing components in future fusion devices , 2005 .

[52]  H. Zohm,et al.  The H-mode density limit in the full tungsten ASDEX Upgrade tokamak , 2014 .

[53]  Jet Efda Contributors,et al.  Preparing the scientific basis for an all metal ITER , 2011 .

[54]  V. Philipps Tungsten as material for plasma-facing components in fusion devices , 2011 .

[55]  Julien Fuchs,et al.  Impurity behaviour in the ASDEX Upgrade divertor tokamak with large area tungsten walls , 2002 .

[56]  J. B. Lister,et al.  Actuator and diagnostic requirements of the ITER Plasma Control System , 2012 .

[57]  R. Wenninger,et al.  Observation of different phases during an ELM crash with the help of nitrogen seeding , 2014 .

[58]  Julien Fuchs,et al.  High-accuracy characterization of the edge radial electric field at ASDEX Upgrade , 2013 .

[59]  Jong-Kyu Park,et al.  Control of asymmetric magnetic perturbations in tokamaks. , 2007, Physical review letters.

[60]  R. Neu,et al.  Plasma-wall interaction and plasma behaviour in the non-boronised all tungsten ASDEX Upgrade , 2009 .

[61]  V. Rohde,et al.  Formation of ammonia during nitrogen-seeded discharges at ASDEX Upgrade , 2012 .

[62]  H. Greuner,et al.  Solid tungsten Divertor-III for ASDEX Upgrade and contributions to ITER , 2015 .

[63]  R. Felton,et al.  Fuel retention studies with the ITER-Like Wall in JET , 2013 .

[64]  C. Angioni Gyrokinetic study of the impact of the electron to ion heating ratio on the turbulent diffusion of highly charged impurities , 2015 .

[65]  H. Greuner,et al.  High heat flux facility GLADIS:: Operational characteristics and results of W7-X pre-series target tests , 2007 .

[66]  David R. Smith,et al.  A study of molybdenum influxes and transport in Alcator C-Mod , 2001 .

[67]  Rohde,et al.  The tungsten divertor experiment at ASDEX upgrade , 1996 .

[68]  T. Eich,et al.  Inter-ELM power decay length for JET and ASDEX upgrade: measurement and comparison with heuristic drift-based model. , 2011, Physical review letters.