The EFDA Programme Duarte Borba

1. The EFDA Programme Duarte Borba

2. OUTLINE • Introduction to EFDA • EFDA Programme • Latest Results and Future Programme • JET • ITER Physics • Power Plant Physics and Technology (PPPT) • Summary and Conclusions

3. OUTLINE • Introduction to EFDA • EFDA Programme • Latest Results and Future Programme • JET • ITER Physics • Power Plant Physics and Technology (PPPT) • Summary and Conclusions

4. Organization of EU programme • European Fusion Development Agreement (EFDA) • Agreement between all EU fusion labs and Euratom • Coordinated research (physics in support to ITER, longer term technology) and JET • Garching (D) and Culham(UK) • Joint Undertaking for ITER “Fusion for Energy” (F4E) • Domestic Agency to provide and manage EU contribution to ITER • EU Contribution to Broader Approach • Located in Spain (Barcelona) Associations: European Fusion Laboratories associated to Euratom through “Contracts of Association” The overall fusion programme is coordinated in the frame of EURATOM

5. EFDA All EU Laboratories/Institutions working on Fusion are parties to EFDA • Collective use of JET (~60M€/y operation + ~5M€/y exploitation + enhancements) • Coordination of focussed physics and technology activities (~5M€/y priority support mobilizing ~25M€/y) • Training (goal ~ 40 new trainee/y) • EU contributions to international collaborations outside F4E JET operated through a JET Operation Contract between the European Commission and the UK Atomic Energy Authority

6. EFDA Organization EFDA Leader/ Associate Leader for JET F. Romanelli Senior Advisor (Int. Collaborations) D. Borba Administration C. Soltane Public Information P. Nieckchen JET L. Horton ITER Physics R. Neu (From July 2012) Power Plant Physics & Technology G. Federici

7. OUTLINE • Introduction to EFDA • EFDA Programme • Latest Results and Future Programme • JET • ITER Physics • Power Plant Physics and Technology (PPPT) • Summary and Conclusions

8. Carbon era of JET ended in 2009 8

9. Be/W ITER-like Wall completed 9

10. Bulk W W-coated CFC 10

11. Neutral Beam Enhancement Project • PINI Performance • Neutralisation efficiency measurements on Octant 8 beamline confirmed that the design goal of >2.13 MW per PINI (>34 MW of total NBI power) can be achieved. View through assembled duct in Assembly Hall, and installed in Torus

12. Long Term Fuel Retention Predicted for ITER 10x (4 months)

13. Long Term Retention: rate normalised to divertor time JET wall temperature ITER 10x JET-ILW: Is the absolute value low enough? True long term value could be much lower (surface analysis) JET C-wall & ILW NBIH-mode Type I ICRHH-mode Type III L-mode 10x

14. Total radiated power Zeff~1.2 n/nGreenwald~80% Line integrated ne Central Te H98 N~2.810% Scenarios: Hybrid plasma JET-ILW: H98~1 also achieved in low and high shape inductive scenarios  H98 ~1 requires low fuelling but W control restricts operating window  Next: Higher power, ELM pacing and central heating (as AUG-W)

15. JET-ILW: Separatrix power threshold LH Threshold with ILW JET-ILW: Total power threshold ILW shown unpredicted strong effect on pedestal and ELM behaviour

16. Possible Scenario (2011-2018/20) ITER preparation with all the control tools foreseen in ITER 2011 2012 2013 2014 2015 2016 2017 2018 2019 2020 ITER Construction Operation Two possible enhancements have been studied: Electron Cyclotron Heating System (ECRH) Resonant Magnetic Perturbation (RMP) coils Start of Enhancement Projects RMP ECRH JET SD Ph2 Ph2 Phase 1 SD SD SD * ITER preparation with tritium plasmas Ph3 DT Ph3 DT Interleaved deuterium, full tritium, trace tritium and high neutron yield DT Campaigns JT60SA Commissioning In Hydrogen Commissioning and Joint experiments Construction SD = Shut down Launched Under further discussion Proposed * Exact duration to be quantified

17. Plasma Stability and Control Edge Perturbation Coils for Plasma Stability Coils independently driven (in pairs) at up to ± 60 kAt Can large (~1MJ) ELMs be suppressed ? Do n=4 and n=3 Resonant Magnetic Perturbations have the same effect ? Does a Be wall affect the ELM suppression ? Does the RMP affect the alpha particle confinement ?

18. Possible JET DT experiment after 2015 10 MW NBI Type I T • Test ITER operation regimes with tritiumabout 10 years before first ITER DT experiment. pedestal pressure (kPa) D Type III • Isotope dependence of confinement • ITER relevant Ion Cyclotron heating techniques with tritium • Diagnostic techniques relevant for DT operation in ITER

19. OUTLINE • Introduction to EFDA • EFDA Programme • Latest Results and Future Programme • JET • ITER Physics • Power Plant Physics and Technology (PPPT) • Summary and Conclusions

20. EFDA ITER Physics Programme • EFDA/F4E Collaboration on JT60SA EU Physics Activities • High Performance Computing

21. MHD Modelling of RMP screening with plasma flows CEA Equilibrium radial electric field with diamagnetic 2 fluids effects in JOREK. vacuum case Islands screening by rotation First tests results on screening of RMPs by toroidal and diamagnetic flows were obtained for JET-like parameters (EFCC coils, n=2,96kAt),

22. Transport Multi-scale turbulence (modeling) ULB, IPP Free energy injection spectra for the fourth-order model (M4) at reduced resolution, compared with a highly resolved DNS. • Large Eddy Simulation tehcnique applied to gyrokinetics in GENE [Banon Navarro PRL 11, Morel PoP 11 & 12] • Progress towards reliable multi-scale simulations at reduced numerical cost [ Morel PoP 12 ]

23. Transport CEA • TORE SUPRA: measurements of extended wave number spectra enable validation of models for multi-scale turbulence, and turbulence simulations Multi-scale turbulence (experiment) GENE [ Vermare PoP & EPS 2011 ]

24. Heating and Current Drive Modelling of RF Sheath and power coupled to Plasma ENEA Modeling of scrape-off plasma with TOPICA and TOPLHA validation of the ITER and other IC and LH antenna design in plasma regimes with different scrape off layer density decay length. AUG antenna has been simulated in details. Assumed SOL Density Profile Modelled Power coupled to plasma

25. PWI Task Force High-Z Materials FZJ Limiter with tungsten lamellae insert before exposure to TEXTOR plasma boundary Measured height profile along W surface after melting by excessive heat flux in TEXTOR discharge with computed height profile obtained by a MEMOS code simulation.

26. ITM Task Force Legacy software structure Anatomy of Modular codes 26

27. Equilibrium chain Kepler Workflow • Standardized module interfaces: • allow for simple construction of generic workflows Access to database 38th EPS 2011, June 27 – July 1, C. Konz 27

28. Equilibrium chain Kepler Workflow • Standardized module interfaces: • allow for simple construction of generic workflows • easy interchange of modules from same type of physics Equilibrium reconstruction: free boundary equilibrium module 38th EPS 2011, June 27 – July 1, C. Konz 28

29. Equilibrium chain Kepler Workflow • Standardized module interfaces: • allow for simple construction of generic workflows • easy interchange of modules from same type of physics Equilibrium refinement: high resolution fixed boundary equilibrium module 38th EPS 2011, June 27 – July 1, C. Konz 29

30. Equilibrium chain Kepler Workflow • Standardized module interfaces: • allow for simple construction of generic workflows • allow for generic visualization of results, e.g. Python, VisIt Generic visualization using Python scripts 38th EPS 2011, June 27 – July 1, C. Konz 30

31. First-principle turbulence codes workflow running on HPC Demonstrated Kepler workflow, using experimental/synthetic JET data, coupling the equilibrium code Helena and the gyrofluid turbulence code GEM. GEM is executed in batch on the HPC-FF

32. Core-Edge Coupling Te in the Scrape-Off Layer computed by SOLPS Te in the core computed by ETS (coreprof  edge) Visualized in the ASDEX Upgrade device geometry Raw geometry data provided by IPP Garching (T. Lunt), Postprocessing done at Aalto University, Helsinki (T. Kuoskela) Simulation and integrated visualization performed at IPP Garching (H.-J. Klingshirn), Using VisIt visualization software and general-purpose ITM tools

33. Diagnostics and RT Control Reflectometer plasma position control IPP, IST Reflectometer plasma position control was achieved both in L and type-I ELMy H–Mode phases. The shaded regions show the discharge phases in which reflectometry separatrix estimate replaced the magnetics as the radial outer plasma position source for feedback control. The solid black lines show the pre-programmed plasma position controller target trajectory. The green curves show the magnetic separatrix position and the red the reflectometry estimates for the outer separatrix position.

34. EFDA/F4E Collaboration on JT60SA EU Physics Activities • EU Research Unit Coordinator is Gerardo Giruzzi (CEA). • Joint EU-JP revision of the JT60-SA research plan completed in 2011 with the issue of version 3.0. • Meeting to finalise the activities for 2012 will take place in in Frascati, 4 – 5 June 2012.

35. EFDA/F4E Collaboration on JT60SA EU Physics Activities • 2012 Work Programme focus on: • General subjects • Follow-up of Research Plan revision, • Modelling of JT-60SA plasmas (performed by the ISM project ) • Definition of JT-60SA data system, validation and analysis tools • Experiments and data analyses on EU machines in support of JT-60SA • Specific subjects • Evaluation/optimization of the ECRH launcher • Assessment of selected diagnostic systems • Assessment of JT-60SA divertor pumping system

36. High Performance Computing HPC-FF Julich, Germany • Total of 68 projects awarded CPU time in 2011 and 60 projects in 2012 Comparison of the filamentation of the plasma during an ELM in the MAST tokamak

37. High Performance Computing HPC-FF Julich, Germany HPC-FF Usage since Production Started in August 2009 • HPC-FF now basically full (some idle time necessary to queue-in large CPU jobs)

38. High Performance Computing IFERC Computer (Helios), Rokkasho, Japan • According the Terms of Reference of the Standing Committee governing the usage of the IFERC supercomputer in Rokkasho, 20% of the time will be allocated directly to the parties (10% for each of the EU and Japan) to enable them to do tests, tuning or adaptation of codes, etc. The parties will internally organise the use of this time, which is available since 9th April 2012. • The remaining time 80% is allocated to projects. • 58 Proposals were accepted and allocated 20.45 M Node Hours in the 1st Cycle of operation • Deadline for proposals for the Second Cycle is end of July 2012. http://www.iferc.org/csc/for-researchers/hpc-information.html

39. High Performance Computing IFERC Computer (Helios), Rokkasho, Japan After discussions with F4E it is agreed that the 10% of time for the EU will be allocated according such as each Associate receives 800 000 CPU core hours (50 000 node Hours), for use by fusion researchers in their country. The same contact persons, as used for the HPC-FF Association accounts, administer the Helios accounts. For TEKES the contact person is Jukka Heikkinen (jukka.heikkinen@vtt.fi)

40. OUTLINE • Introduction to EFDA • EFDA Programme • Latest Results and Future Programme • JET • ITER Physics • Power Plant Physics and Technology (PPPT) • Summary and Conclusions

41. System code Studies for optimisation of Fusion power plant DEMO concepts • For pulsed operation, the main aspects of concern at present are the flux swing, pulse length and divertor heat load modelling, although there are some concerns about cyclic fatigue issues, which are not well captured in systems studies at present. • In modelling steady-state devices, the main concern at present is the divertor heat load and radiation modelling. Conservative Advanced • These studies should lead to improved modelling but also to new experimental work to validate key assumptions such as the impact of radiation on confinement, plasma behaviour at high density and high β.

42. Assess Prospects for Alternative Concepts for Heat Removal in Fusion Reactors • Capillary porous systems (CPS) • Optimize heat extraction without evaporation cooling for Li systems in magnetic confinement devices. • Test the resilience to transients loads (disruptions, ELMs) • Test other material options (e.g. Ga, Al, Sn) • Droplet systems • Check stability of droplet systems in magnetic confiment devices and in test stands with high magnetic fields • Liquid metals, basic properties • Identify temperature window with low evaporation and low tritium retention (mainly Li) • Understand T retention mechanism • Decide on reactor compatibility

43. High Temperature Super Conductors • REBCO (rare-earth barium-copper-oxide high-temperature superconductors) is the only candidate for application for fusion magnets • Demonstrators have shown currents up to 7.5 kA (77 K, self field) • Operation at 4 K and fields in the range of 12 T - 18 T is possible and allows • e.g. 74 kA @ 4 K and 15 Tesla • 30% volume reduction of winding pack • Effective current closer to the plasma -> higher field • The higher cost for REBCO could be partially balanced by simpler structure (no radial plates), no SC annealing andsimpler HV insulation of the cable

44. Remote Handling • In-vessel gamma radiation dose levels of ~20kGy/hr after 2 fpy will prohibit the operation of many remote handling technologies within the Tokamak • The Vertical Maintenance System with Multi Module Segment (MMS) is considered to be the most viable plant architecture for power plant relevant maintenance • Due to the harsh conditions predicted within the tokamak, ex-vessel remote operations need to be maximised to minimise those required in-vessel and planned in-vessel maintenance should not include any complex operations, i.e. cutting and welding.

45. Material Programme in EFDA The materials programme in EFDA is being reoriented along three main lines: • DEMO materials choices and specifications: • DEMO 2030 will probably need to use “existing” materials (e.g. EUROFER) • Reconsider Cu-alloy for a water-cooled divertor. • guidance of test matrixes for irradiation campaigns • design of material irradiation experiments to consolidate the materials database for DEMO structural materials using existing fission reactors (e.g., by using isotopic tailoring) dual ion-beams, modelling of radiation effects, exploitation of post-EVEDA irradiation campaigns • development of improved materials for later fusion devices • Tungsten and tungsten alloys • Oxide-dispersion-strengthened ferritic steels (ODSFS) • Material modelling.

46. Summary • JET • The ILW JET shutdown was completed • First results confirm low tritium retention • Operation with the ILW achieved more easily then expected • Good H-mode confinement discharges established • The ITER-like Wall has shown • Anticipated benefits and risks of a W/Be wall: • Large reduction in fuel retention and very clean/reproducible plasmas • ITER scenarios constrained by W-accumulation but still achievable • Good power handling and protection of the Be/W wall • An unpredicted strong effect on pedestal and ELM behaviour

47. Summary • ITER Physics EFDA programme covers a number of key physics priority questions for ITER exploitation: • MHD, Transport, H&CD, PWI, ITM, Diagnostics • Preparation of the operation of JT60-SA together with Japan • Management of Super Computer Resources (HCP-FF and Helios) • Power Plant Physics and Technology (PPPT) activities: • System code Studies for optimisation of Fusion power plant DEMO concepts • Concepts for Heat Removal in Fusion Reactors • High Temperature Super Conductors for Fusion Applications • Remote Handling • Fusion Materials Research

48. Thank you for attention

49. Backup Slides

50. EFDA 2012 Work Programme Implemented under Cross Topical Areas of Research Prediction of Material Migration and Mixed Material Formation (PWI, DIA) Shaping and controlling performance limiting instabilities (MHD, DIA, H&CD-F) Fuel Retention and Removal (PWI, DIA, H&CD-F) Plasma rotation (MHD, TRA, H&CD-F) Core electron heat transport and multi-scale physics (TRA,DIA) Pedestal instabilities (ELMs), Mitigation and Heat loads (MHD, TRA, PWI, DIA, H&CD-F) Disruptions, prediction, avoidance, mitigation and consequences (MHD, PWI, DIA) Physics of the Pedestal and H-mode (DIA, TRA, H&CD-F) Fast Particles (MHD, TRA, DIA, H&CD-F) Particle transport, fuelling and Inner Fuel Cycle modelling (TRA, H&CD-F, PWI) Operation with metallic plasma facing components, including High Power ICRH (PWI, H&CD-F)