Overview and challenges of the ITER Project

1. Overview and challenges of the ITER Project Lecture at Instituto Nazionale di Fisica Nucleare 24 February 2009 Norbert Holtkamp Principal Deputy Director General of the ITER Organization

2. Global Warming and How much is left? Oil reserves 60 000 year CO2 level

3. Fusion powers the sun and the stars“…Prometheus steals fire from the heaven” • Essentially limitless fuel, available all over the world • No greenhouse gases • Intrinsic safety • No long-lived radioactive waste • Large-scale energy production On Earth, fusion could provide:

4. The Fusion Reaction on Earth“... is not the same as in the Sun“ • CH4 + 2O2 --> CO2 + 2H2O + 5.5 eV (chemical) • 41H + 2e --> 4He + 2 + 6  + 26.7 MeV (solar process)

5. Why D-T: Cross section

6. Fusion in the Universe =3x109atm

7. Fusion History: The Russian Point of View… • 1928.G.Gamov -the theory • 1930.Olifant,Kurchatov,Sinelnikov, exp.- proton beam, Li target • 1932.Bucharin proposals to Gamov: Moscows electricity every night! • Gamov left USSR • 20 years pausa • …..not quite correct!!! E. Velikhov; AAAS 2008 Annual Meeting

8. What did the Fusion Community Promise? A short history of Fusion • E = M * C2 • 1900: “the Mass deficit” on the sun • 1920: Hydrogen to Helium “burning” process was speculated • 1928: Gamow uses “tunnel effect” to explain fusion • 1934: Rutherford D+T=>He • C.F. Weizsäcker/H.Bethe: Proton-Proton chain • 1939: H. Bethe,’Energy Production in Stars’; Nobel P 1968 • 1945: Fermi+Teller: Magnetic confinement of hot plasmas • 1946: first patent in Britain • 1951: Péron and the Stellarator; R. Richter: Austrian/German • 1951: L. Spitzer: Stellarator experiment in Princeton. – • 1950: Sacharow+Tamm first linear device: • 1955: first TokamakTMP • 1955: J.D. Lawson: “Lawson Criterion” • 1957: ZETA • 1958: Kurchatov announced effort of Nuclear Fusion • 1968: L.Artsimowitsch: “Confinement” and the way to “break” even. • Europe: 1958 foundation of Euratom and the way to JET which was planned in England, thought to be build in Garching and finally began operation in 1983 in Culham. • Chernobyl disaster led to a decreased interest in nuclear energy…(56 direct death, 47 emergency workers, ~6000 cancer cases) • In the middle of the ’90s: price per barrel ~20$, and very little investment was done in alternative energies… The dangling “Carrot” ….

9. Basic Principle of Stable Motion of Ions in Magnetically confined Plasma

10. Tokamak and Stellarator "тороидальная камера в магнитных катушках" (toroidal'naya kamera v magnitnykh katushkakh) — toroidal chamber in magnetic coils (Tochamac)).

11. The 40’s-50’s: ZETA The First Devices IAEA: 1958 First Geneva Conference

12. Lawson: The Fusion Equation • Confinement Time • Density • Temperature

13. Lithium compound A Fusion power plant would be like… Not to scale !

14. The Basic Tokamak

15. ITER Plasma Scenario - ELMy H-mode • Conventionally, plasma confinement regimes denoted L-mode and H-mode • The difference between these modes is caused by the formation of an edge pedestal in which transport is significantly reduced - edge transport barrier • edge localized modes maintain plasma in quasi-stationary state JET

16. History of Tokamak’s TRIAM, J EAST, China

17. SST-1: R =1.1m, 0.22MA, 2008 Four New Superconducting Tokamaks will Address Steady-State Advanced Tokamak Issues in Non-Burning Plasmas EAST: R = 1.7m, 2MA, 2006 JT-60SA: R = 3m, 5.5 MA, 2014 KSTAR: R = 1.8m, 2MA, 2008

18. ITER – Key Facts • Mega-Science Project among 7 Members: • China, EU, India, Japan, Korea, Russia & US • Designed to produce 500 MW of fusion power for an extended period of time • Will bring together most key technologies needed for future fusion power plants • 10 years construction, 20 years operation • Cost:~5 billion Euros for construction, and ~5 billion for operation and decommissioning

19. The Way to Fusion Power – The ITER (Hi-)story “For the benefit of mankind ” The idea for ITER originated from the Geneva Superpower Summit in 1985 where Gorbachev and Reagan proposed international effort to develop fusion energy… …“as an inexhaustible source of energy for the benefit of mankind”. November 21, 2006: China, Europe, India, Japan, Korea, Russian Federation and the United States of America sign the ITER Agreement

20. …based in Cadarache, Southern France

21. PDDG house

22. JET/JT-60/TFTR → ITER

23. MAST JET: The Key Facility • JET: 16 MW of fusion power ~ equal to heating power. • Ready to build a Giga Watt-scale tokamak: ITER

24. ITER Tokamak – Mass Comparison Charles de Gaulle mass: ~38000 t(empty) 856 ft (261 m) long (Commissioned 2001) ITER Machine mass: ~23000 t 28 m diameter x 29 m tall

25. The core of ITER Machine mass: 23350 t (cryostat + VV + magnets) - shielding, divertor and manifolds: 7945 t + 1060 port plugs - magnet systems: 10150 t; cryostat:  820 t

26. Vacuum Vessel Mass Comparison VV & In-vessel components mass:~8000 t 19.4 m outside diameter x 11.3 m tall Eiffel Tower mass:~7300 t 324 m tall (Completed 1889)

27. ITER R&D before 2001 in Industry

28. Key Design Review Issues - Tokamak PF/CS performance: shape and vert. stability Vacuum vessel em-loads H&CD Systems Blanket/ First Wall design and RH- Heat Loads Internal coils: ELM & RWM control,Vertical stability Divertor material strategy TF performance: fusion gain

29. Major Risk Reduction implemented in the ITER design

30. Major Adaptations • Physics: ELM coils / vertical stability are addressed together with Resistive Wall Mode (RWM) mitigation. • Vacuum Vessel: major change due to In Vessel coils for ELM / VS / RWM stabilization. Improve supports to deal with higher vertical + horizontal forces. • Magnets: Poloidal Field (PF) current carrying capability of new conductor design allows increase of field by 15-20%. PF6 to include extra double pancake and include sub-cooling. Increase PF2 turns by 10%. • Heating&Current Drive major changes: • Independent set up for Padua Neutral Beam facility needs independent infrastructure and components • Evaluation of Start up scenario shows that 127GHz / 3 MW start-up system is not necessary • In Vessel Components: Several adaptations and changes: • Blanket attachment and water cooling manifold • Tiling adjustment of first wall in several areas to deal with misalignments and heat loads • Buildings: as part of the site adaptation changed the site and building layout minimizing the overall cost. Nevertheless, for the hot cell and the tokamak complex, increase due to commodity cost seem unavoidable.

31. Conceptual: ELM/ VS Control by internal Coils in ITER VS • An internal set of resonant magnetic perturbation (RMP) and vertical stabilization coils under design • Looked at other options: Outside, between the shells + inside

32. ELM & VS coils – layout of reference option VAC-02 - 3 rows – 9 coils Upper feeder Upper VS coil VS toroidal connecting leg Upper ELM coil mid coil (space limited) 40° sector Outboard Lower ELM coil • “Multi purpose” in vessel coils: • - ELM control (2Hz), • Vertical Stability control • Radial position control • Resistive Wall Mode (RWM) control • (25 Hz) Lower VS coil

33. VV and In-vessel Components

34. Blanket Status & Accomplishments Status & Accomplishments • Generic blanket / FW design in progress • Improved FW shaping in progress (will allow removal of moveable limiters) • Qualification of mock-ups ongoing with first successful results • EM analysis benchmarking in progress • RH design of hydraulic connection in progress • Thermal & mechanical loads updated and finalized

35. Blanket Activities Developing Simplified Hydraulic Connector Thermal loads have been updated 2.2 MWm-2 at 5° Developing single FW panel to reduce number of operations Shaped to shadow leading edges, and shield access holes Horizontal fingers to reduce Halo and Eddy loads Fingers to simplify manufacture, and permit other heat flux technologies Bolted mechanical connection Developing in-vessel separable First Wall No additional cutting/welding in hot cell No additional access holes for Shield Block mounting

36. TF Coil – Mass Comparison Mass of (1) TF Coil: ~360 t 16 m Tall x 9 m Wide D8 Caterpillar Bulldozer ~35 t

37. Overview of the Magnet System • 48 superconducting coils • 18 TF coils • 6 CS modules • 6 PF coils • 9 pairs of CC

38. Scope of ITER Conductor Supply Bronze Nb3Sn strand developed by EAS, EU Internal-tin Nb3Sn strand developed by OST, US NbTi strand developed by VNIINM, RF TF Conductor PF Conductor

39. Jacketing Lines • Longest lead item is the setting up of jacketing lines. (Courtesy of Wu Yu, ASIPP) Civil Engineering Work at ASIPP, CN (TF & PF) (Courtesy of A. Taran, VNIKP) Civil Engineering Work at UNK under VNIKP Supervision, RF (TF)

40. Pre-Compression Ring Test @ Frascati Test bed to test up to 1400 MPa while 350 is needed in ops

41. Poloidal Field Control in ITER • Slow feedback loop through PF coil system: • control of plasma current, shape, • coil currents, separatrix separation, etc. (5-10 s) • Fast feedback loop through in vessel coil: • stabilization of plasma vertical position (<1 s) • General Improvements in the PF systems, especially PF6 through increase in current and size VS VS

42. The original scenario envisaged an aperture expansion ramp up: resultant peaking of current profile challenging for for vertical stabilization system possibility of reaching CS current limit before start of burn The possible solution is to: break down in the centre/inboard of the vacuum vessel for full bore plasma; form the divertor configuration as early as possible; and apply additional heating during the current rise (li control to lower li). Possibly remove limiters Also: The 127 GHz start-up system is not required anymore Modified Plasma Start-up

43. Backup Design – “Blanket Assembly” • VDE Pressure loads that before acted on the VV here act on the blanket assembly. • High machining precision - VV schedule impact • Modules are structurally assembled ( saw teeth) to a single shell self-supporting structure inside the vessel. •  No differential thermal expansion between adjacent modules. • Simpler supports: 4 rows of keys similar to divertor rail  no support housings required. • Machining precision of first wall shape.

44. Strategy for the use of plasma facing materials in ITER has been revised: CFC will be used for high heat flux regions of divertor in advance of DT phase tungsten targets will be installed before DT operation. May be from the beginnig Substantially reduces potential limitations in operation due to tritium co-deposition with carbon Also a new divertor dome design as mentioned before. Plasma Facing Material: Strategy Divertor Cassette Baffles Dome Targets - high heat flux

45. CFC divertor targets (~50m2): erosion lifetime (ELMs!) and tritium co-deposition dust production Be first wall (~700m2): dust production and hydrogen production in off-normal events melting during VDEs W-clad divertor elements (~100m2): melt layer loss at ELMs and disruptions W dust production - radiological hazard in by-pass event Plasma Facing Material Strategy

46. Tritium Plant Building Systems Layout

47. Section view ~ 100 persons city bus Tokamak Building Hot Cell Building Tokamak lift cask cask RHTS Cask cask Cask Cask cask Above ground Cask Cask Rock level <- Full basement ->

48. Lay Out Of The Neutral Beam Test Facility in Padua ITER NB Heating System 1 MV DC ~40 A of H- current 20 MW delivered to Plasma Up to 3 systems on ITER Neutral Beam Test Facility

49. ITER Buildings and Facilities Cryoplant – 65 kW at 4.5 K & 1300 kW at 80 K Second largest in world PF WindingBuilding – ~250 m (820 ft) x 45 m (148 ft) Tokamak & Assy building – 6 levels @ 166 m x 81 m x 57 m high (~36000 m2) Magnet power convertors buildings (~1000 MW output power) Tritium building – 7 levels @ 25 m x 80 m (~14000 m2) Largest throughput in world (~300 kg/yr). Hot cell – 60 m x 70 m Area - 60 hectares (~150 acres)

50. ITER Organization