Kein Folientitel

Kein Folientitel

ASDEX Upgrade: Progress and Plans Hartmut Zohm for the ASDEX Upgrade /EUROfusion MST1 Teams* Max-Planck-Institut fr Plasmaphysik, Garching, Germany *see e.g. appendix of H. Zohm et al, Nucl. Fusion 55 (2015) 104010 Presented at Fusion Power Associates meeting, Washington DC, USA, 13.12.2016 A Programme in Preparation of ITER and DEMO Solving immediate questions aiding the detailed ITER design guide ITER design in areas where input is still missing (ELMs, disruptions, first wall components) Preparing ITER operation

prepare to address new physics: dominant a-heating develop operation scenarios that ensure baseline operation (Q=10) and make possible advanced operation (Q > 10 or steady state) Developing and improving the physics base for DEMO DEMO is a point design need first principles understanding to build numerical tokamak (strong interaction with theory) address areas which are crucial for DEMO byond those for ITER (n/ nGW > 1, high core radiation fraction etc.)

Educating fusion plasma scientists train and educate the generation that will run ITER AUG Programme in support of ITER and DEMO ITER DEMO (EU example) Q=10: bN=1.8, H=1, n/nGW=0.85 Q30: bN=3.5, H=1.2, n/nGW=1.2 Psep/R = 15 MW/m, Prad,core/Ptot=0.3 Psep/R = 15 MW/m, Prad,core/Ptot=0.75

Large type I ELMs not allowed No ELMs allowed (?) Very small number of disruptions Virtually no disruptions ASDEX Upgrade and JET form a step ladder to ITER ASDEX ASDEXUpgrade Upgrade JET JET ITER ITER

Geometry similar to ITER, linear dimensions scale 1:2:4 ASDEX Upgrade has a powerful H&CD system Ion Cyclotron Resonance Heating: 7 (8) MW @ 30-60 MHz Neutral Beam Injection: 20 MW @ 60/93 kV NBCD by tang. beams Electron Cyclotron Resonance Heating: 5 (8) MW @ 140/105 GHz Exhaust Exhaust studies

studies at at high high P/R P/R b-limit b-limit accessible accessible at at any any field field ECCD ECCD for for MHD MHD control control ASDEX Upgrade has pioneered W-wall operation P92 tiles (chemistry

and ferromagnetism similar to EUROFER) massive tungsten tiles (outer divertor) all other PFCs are W-coated C-tiles learned how to keep W-concentration low at high plasma performance instrumental in changing ITER PFC strategy (together with JET ILW) 2 x 8 off-midplane saddle coils for MHD control

static / rotating fields up to 500 Hz, at n = 1, 2, (3), 4 continuous poloidal phase scan at constant n Main Programmatic Lines on ASDEX Upgrade Exhaust scenario for ITER and DEMO (partially) detached divertor operation at high Psep/R (ITER&DEMO) high core radiation with good fusion performance (DEMO) assessment of advanced divertor configurations (DEMO) Core scenarios for ITER and DEMO

maximum fusion power low q95 (ITER) steady state tokamak operation higher q95 (ITER and DEMO) mitigation or suppression of ELMs and disruptions (ITER and DEMO) Note: underlying theme is the development of first principles physics understanding needed for safe extrapolation ongoing effort to improve diagnostic systems and compare with theory and modelling (example: fast particles)

Main Programmatic Lines on ASDEX Upgrade Exhaust scenario for ITER and DEMO (partially) detached divertor operation at high Psep/R (ITER&DEMO) high core radiation with good fusion performance (DEMO) assessment of advanced divertor configurations (DEMO) Core scenarios for ITER and DEMO

maximum fusion power low q95 (ITER) steady state tokamak operation higher q95 (ITER and DEMO) mitigation or suppression of ELMs and disruptions (ITER and DEMO) Note: underlying theme is the development of first principles physics understanding needed for safe extrapolation ongoing effort to improve diagnostic systems and compare with theory and modelling (example: fast particles) Exhaust: impurity seeding at high input power

A. Kallenbach et al., Nucl. Fusion (2012) A. Kallenbach et al., Nucl. Fusion (2015) ITER like: N-seeding DEMO like: N- and Ar-seeding core radiation fraction ~ 30% core radiation fraction ~ 70 % Psep/R=10MW/m, Ptarget=3 MW/m2 Still H=1, bN=3

Exhaust: present and future capabilities Extension of H&CD capabilities will allow to simultaneously inject 34 MW H. Zohm et al., Nucl. Fusion 2015 Exhaust: Planned upgrade of upper divertor (2020) T. Lunt et al., PSI 2016 A. Herrmann et al., PSI 2016 Flexible in-vessel coil set to study physics elements of advanced divertors X-divertor, Snowflake divertor and Double Null can be studied Lower divertor kept untouched for ITER reference operation

Main Programmatic Lines on ASDEX Upgrade Exhaust scenario for ITER and DEMO (partially) detached divertor operation at high Psep/R (ITER&DEMO) high core radiation with good fusion performance (DEMO) assessment of advanced divertor configurations (DEMO) Core scenarios for ITER and DEMO

maximum fusion power low q95 (ITER) steady state tokamak operation higher q95 (ITER and DEMO) mitigation or suppression of ELMs and disruptions (ITER and DEMO) Note: underlying theme is the development of first principles physics understanding needed for safe extrapolation ongoing effort to improve diagnostic systems and compare with theory and modelling (example: fast particles) Core scenarios: ITER baseline Q=10 at q95=3

J. Schweinzer et al., Nucl Fusion 2016 Significant impact of all-metal wall on operational window decreased pedestal performance (ne(r) shifts outward with high gas puff) suggests a shift of the Q=10 operation scenario to higher bN, higher q95 similar findings on JET with the ITER-like wall (ILW) Core scenarios: steady state high performance Resonable bootstrap fraction (~ 50%), fully noninductive A. Bock et al., EPS (2016) stationary on the current redistribution timescale, starting from relaxed q(r) MHD stable at high b for decent q95 (~5.5) Scenarios: ELM suppression by RMPs

full ELM suppression at low n*. (similarity experiment with DIII-D) no accumulation of W at pedestal top (!), slight reduction in confinement important role of plasma shape! W. Suttrop, EPS 2016, R. Nazikian, IAEA 2016 Core scenarios: NTM suppression by ECCD M. Reich et al., IAEA 2014 Feedback system targets multiple mode control for disruption avoidance Core scenarios: NTM suppression by ECCD M. Reich et al., IAEA 2014 Feedback system targets multiple mode control for disruption avoidance

Core scenarios: NTM suppression by ECCD M. Reich et al., IAEA 2014 Feedback system targets multiple mode control for disruption avoidance Main Programmatic Lines on ASDEX Upgrade Exhaust scenario for ITER and DEMO (partially) detached divertor operation at high Psep/R (ITER&DEMO) high core radiation with good fusion performance (DEMO)

assessment of advanced divertor configurations (DEMO) Core scenarios for ITER and DEMO maximum fusion power low q95 (ITER) steady state tokamak operation higher q95 (ITER and DEMO) mitigation or suppression of ELMs and disruptions (ITER and DEMO) Note: underlying theme is the development of first principles physics understanding needed for safe extrapolation

ongoing effort to improve diagnostic systems and compare with theory and modelling (example: fast particles) Fusion physics: fast particle investigations red-shifted blue shifted 5 FIDA (Fast Ion D-Alpha) views intersecting heating beam #3 Weight functions cover different parts of velocity space with radial resolution Tomographic deconvolution in velocity

space yields estimate of f(E,v||/v) Fusion phyiscs: tomography in velocity space TRANSP/NUBEAM 60 keV NBI only TRANSP/NUBEAM 60 & 93 keV NBI FIDA Tomography 60 keV NBI only FIDA Tomography 60 & 93 keV NBI M. Weiland et al., PPCF 2016

Basic features well reproduced, future: 6-D phase space physics Conclusion - timeline ASDEX Upgrade has a strong programme in support of ITER and DEMO combination of programmtic and curiosity driven scientific approach The planned extensions will enable us to significantly contribute to the EUROfusion Roadmap Missions 1 and 2 beyond 2020 collaborations (both EU/MST and international) are an important element

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