Finnish Contributions to Euratom Fusion Programme and ITER

Finnish Contributions to Euratom Fusion Programme and ITER VTT PROCESSES Seppo Karttunen, VTT Association Euratom-Tekes OUTLINE: - Fusion in Europe (FP7) - Euratom-Tekes Fusion Programme in FP7 - Tekes Research Areas Briefly - Physics Transport and Fast Particles - ITER Remote Handling DTP2 Facility - Plasma Wall Interactions - Finnish ITER procurements - Summary

VTT PROCESSES Global Fusion Project - ITER

Fusion in Europe (FP7) VTT PROCESSES 27 Fusion Associations including Tekes CoA Euratom EFDA = European Fusion Development Agreement DEMO Fusion for Energy (F4E) = European Joint Undertaking for ITER and the Development of Fusion Energy JET = Joint European Torus ITER Support Physics PPPT = Power Plant Physics and Technology ITER Construction BA = Broader Approach Structural changes are expected in the FP8 (Horizon 2020) Merging of EFDA and F4E is possible ITER Cost for Europe is 6,6 B (2007-2020)

VTT PROCESSES Euratom-Tekes Fusion Programme in FP7 Fusion technology development in collaboration with Finnish industry for the international ITER project and a focused participation in the accompanying European Fusion Programme. Programme duration: 2007-2011 + 2 years Annual volume: ~ 5 million, corresponding to 40-50 ppy per year RU Institutes: VTT, AU, TUT, LUT, UH, UT (Estonia) and industry

Tekes Research Areas Briefly Physics (CoA, EFDA): VTT PROCESSES JET/AUG experiments and modelling: - transport and edge plasmas - plasma-wall interactions - diagnostics: NPA detectors, magnetometers, - modelling, code integration and development Other EFDA Activities: - Task Force ITM = Integrated Tokamak Modelling - ITER Support Physics - PPPT = Power Plant Physics and Technology EFDA Secondments: - JET Task Force Leader and two Deputies - 1-3 Secondees at JET - 2 ITPA members, - HPC - High Level Support Team

Tekes Research Areas Briefly VTT PROCESSES Technology (F4E, EFDA): Remote handling systems - DTP2 ITER Divertor Test Platform (F4E) - water hydraulic manipulators and tools (F4E) - welding robots (ITER & industry) Materials research - characterisation of in-vessel materials - testing of post-irradiated materials and in-situ testing - joints (HIP, welds) and multi-metal components (F4E) - New steels e.g. ODS steels (EFDA PPPT) - plasma facing materials, coatings and smart tiles (EFDA) - arc cleaning of deposited layers to control T-inventory - LIBS spectroscopy for in-situ FW diagnostics

Tekes Participation in the EU Fusion Programme: Physics and Technology in FP6 VTT PROCESSES 80 70 60 50 40 30 20 10 0 Tekes contribution 0,5% IPP ENEA CEA UKAEA Swiss VR IST Tekes Risö IPP.CR Physics Programme 12000 10000 Tekes contribution 4% 8000 Technology Programme k 6000 Art. 5.1b Art. 5.1a 4000 2000 0 DCU HAS Greece NASTI Latvia IST VR RISØ IPP.CR FOM ÖAW FZJ TEKES Belgium UKAEA CIEMAT SWISS ENEA IPP FZK CEA

Tekes in JET Campaigns

VTT PROCESSES Physics Transport and Fast Particles Energy and particle transport determine the energy confinement and fusion performance Transport in tokamak plasmas is anomalous and well above the (neo)classical transport Anomalous transport is driven by plasma turbulence All means to suppress turbulence will lead to better confinement and fusion performance Plasma rotation (shear flow) is an important mechanism to suppress turbulence Fast particles (e.g. fusion alphas) may drive plasma instabilities and lead to high local heat loads

Euratom-Tekes Association Steering Committee Meeting, 29.10.2010 Developing advanced tools: ELMFIRE Present CSC/DEISA/HPC-FF resources allow massively parallel simulations of middlesized tokamaks up to transport time scale with full-f gyrokinetic code ELMFIRE Recent SOL upgrade of the code may be the final physics element needed for the proofof-principle simulations of triggering mechanism of L-H transition Understanding triggering mechanism of L-H transition is crucial for predicting ITER performance! Successful experimental benchmark of FT-2 turbulence characteristics is now followed by similar work for TEXTOR Active participation in High level support team and ITM Task Force has been found very useful 10

Euratom-Tekes Association Steering Committee Meeting, 29.10.2010 JET and ITER contributions 2010 Several results in JET for transport of plasma momentum and rotation extrapolating ITER rotation better ( two PRL publications). Results presented at IAEA FEC-conference (oral). In JET, ExB drift with an appropriate current profile lowers plasma stiffness. Thus ion temperature and its gradient will be higher. Difficult to see in gyrokinetic simulations (PRL at JET pinboard). DIII-D:n ITER-TBM experiment analysis (IAEA FEC 2010) M. Nave, (including) T. Tala, A. Salmi et al., Phys. Rev. Lett. 105, 105005 (2010)

VTT PROCESSES ASCOT Simulations of Fast Particles ASCOT is a VTT-Aalto based Monte Carlo code which is widely used by EU Fusion Community

VTT PROCESSES

VTT PROCESSES ASCOT Simulations of Fusion Alpha Particles (Aalto) in ITER for various conditions

14.10.2011 15 ITER Remote Handling High radiation dose No human access into reactor vessel Limited camera view Limited choice of materials, sensors, etc. Heavy components Space very limited Remote handling is important to make the ITER project a success Advanced full-scale test platform is needed Reliability of all remote handling operations needs to be verified and tested using real prototypes (Fail safe, Fault tolerant, Recoverable) Maintenance is critical for ITER scientific success

14.10.2011 16 Divertor Test Platform DTP2 DTP2 - the planned divertor maintenance operations to be verified Cassette locking, transportation,.. DTP2 is necessary for developing and testing devices, sequences and operation procedures for ITER maintenance Divertor Divertor Cassette Maintenance Tunnel

14.10.2011 17 DTP2 Test Facility in 2011 Expected lifetime for DTP2 more than 25 years Divertor Region Mock-up (TP-Konepajat, Finland) DTP2 Test Hall (VTT, Finland) Water Hydraulic Manipulator (TUT, Finland) Cassette Multifunctional Mover (Telstar Tecnologia Mecanica, Spain) Divertor Cassette Mock-up (Gradel, Luxembourg) Control Software (TUT and VTT, Finland)

14/10/2011 18 Design, modifications and mock-ups Divertor test platform toroidal extension Cassette toroidal mover New end-effectors for the CMM Standard cass. end-effector Central cassette end-effector Diagnostic rack end-effector Central cassette locking system Cassette locking system Inner attachment Outer attachment

Plasma Wall Interactions VTT PROCESSES Plasma-wall interactions are very important in fusion devices Extremely high particle and heat loads 10-20 MW/cm2 Erosion - material transport deposition Tritium rentention in deposited layers - high T-inventory ruled out Carbon as plasma facing material ITER PFC materials are Be and W Mixed materials issues are important D,T, He, C, Be, W

Finnish PWI Activities VTT PROCESSES Tekes Association has one of the strongest PWI teams in EU Programme Expertise cover: PWI experiments in JET and AUG tokamaks and FOM linear devices (VTT, Aalto) Post-mortem analysis (SIMS) of divertor tiles (VTT) Smart tiles with diagnostic coatings (VTT, Diarc Tech, In-situ LIBS spectroscopy (VTT & Tartu) Edge- and SOL plasma modelling (Aalto, VTT) ERO modelling (VTT) and Molecular Dynamics simulations (UH) Arc cleaning of PFCs (T-inventory control)

08/06/2011 21 Successful and safe operation of future fusion reactors requires sufficiently long lifetime of its plasma-facing materials and components low accumulation of plasma fuel (tritium) in the reactor vessel We have addressed these issues by studying erosion of W and Ni in the ASDEX Upgrade tokamak campaign-integrated erosion data from wall tiles with marker stripes discharge-resolved erosion data with the help of marker probes at specific locations of the tokamak ASDEX Upgrade = full-w machine since 2007 ITER-relevant environment Ni simulates the behavior of steel in a tokamak environment

MD simulation of sputtering in our group Matemaattis-luonnontieteellinen tiedekunta / Katharina Vörtler We have more than 10 years of experience On carbon surface and Swift chemical sputtering: Salonen et al, Europhys. Lett. 52 (2000) 504; Phys. Rev. B 63 (2001) 195415; Behrisch-Eckstein sputtering book vol. 4 A. V. Krasheninnikov, K. Nordlund, E. Salonen, J. Keinonen, and C. H. Wu, Comput. Mater. Sci 25, 427 (2002). K. Nordlund, E. Salonen, A. V. Krasheninnikov, and J. Keinonen, Pure and Applied Chemistry 78, 1203 (2006). On beryllium surface: Björkas et al.,new J. Phys. 11, 123017 (2009) On tungsten carbide surface: Träskelin et al., Phys. Rev. B 75, 174113 (2007) Vörtler et al, J. Phys.: Condens. Matter 23, 085002 (2011) www.helsinki.fi/yliopisto 08.06.11 22

08/06/2011 23 Inner life of ASDEX Upgrade in 2008-2009 upper divertor limiter tiles central heat shield Marker probes inserted into the plasma from the midplane Campaign inner divertor roof baffle outer divertor Number of discharges Plasma time Number of boronizations 2008 726 3530 s 3 2009 1101 5275 s 3 Marker tiles located in the divertor

08/06/2011 24 Marker tiles and their post mortem analyses SIMS (Secondary Ion Mass Spectrometry) 5-keV O 2+ ions, analysis area 0.3 0.4 mm 2 depth profiles of different elements RBS (Rutherford Backscattering Spectroscopy) 2.5-MeV or 3-MeV protons, beam diameter 1.8 mm erosion of the marker stripes Inner divertor W (0.2-1.0 m) Outer strike point C, uncoated W (0.5-1.5 m) W (0.2-1.0 m) C, uncoated Ni (5 m) Outer divertor Ni (2 m) C, uncoated W (0.2-1.0 m)

08/06/2011 25 W eroded by up to 1 m, Ni five times more! Inner divertor Outer divertor Outer divertor outer divertor largest net erosion zone erosion by arcing in the inner divertor net re-deposition in areas below the strike points re-deposition 2 times larger on C than on Ni Largest erosion around the outer strike point, results normalized to 3000 s of plasma time

This image cannot currently be displayed. Plasma facing Components: Erosion/Deposition (Global trends) Dump plate: deposition OPL: Erosion near midplane IWGL: erosion deposition divertor: deposition (inboard) erosion (outboard) P Coad PFMC-13 9-13/5/2011

Erosion/deposition at divertor (MkIISRP, 2001-2004) 27 deposit 3µm W W CFC JG03.676-1c W VTT

JET vessel 2009, 2011 28 2011 Be 2009 C Be C Be C W C

29 Fuel retention at JET Clearly one of the highest priority ITER items (R.A. Pitts, 1 st General Planning meeting for ILW campaigns, Culham, 1-5 March 2010) Tile Amount of D (g) 10 Tile 1 2.0 D/C ratio Tile 3 0.6 1 Tile 7 0.4 Tile 8 1.0 D/C 0.1 0.01 0.001 1 3 4 5 6 7 8 0 500 1000 1500 2000 Poloidal distance around divertor (mm) High D/C ratios found on tiles 1 and 8. D retention on tiles 3 and 7 small Tiles 4 and 6 (not analysed yet) have very very thick films and D inventory is high (most of deposited D retained on these tiles) Overall fuel retention will be determined later

Finnish ITER procurements VTT PROCESSES Cr-Cu strands by Luvata completed Two radial plate protypes were fabricated by different methods - HIPed RP by Metso - more conventional by??? - both protypes were successful RP procurements in near future Remote Handling development (DTP2) RH procurements starting Magnetometer development for F4E (VTT) is ongoing Potential New Items: Other HIP applications for in-vessel components by Metso Welding robot (VTT, LUT) for sector welding CODAC (control systems)

SUMMARY VTT PROCESSES - The Finnish Programme is technology oriented and ITER relevant remote handling, materials, welding - The success in DTP2 work has made VTT and TUT major players in RH technology in Europe - In physics, we participate in the top European fusion experiments havig a very visible and efficient role JET and AUG - Physics topics are the highest priority issues for ITER - In plasma-wall interactions we have one of the best teams in Europe and world wide. - Modelling and code development capabilities are very high (ASCOT, ELMFIRE, MD,...) which keeps our position in fusion physics strong