1. ITER The past, present and future 1985 to 2007 Garry McCracken

2. What is ITER? ITER is a design for a nuclear fusion experiment to demonstrate the feasibility of a fusion power plant. First proposed as a collaboration between the US and the Soviet Union by Ronald Reagan and Mikhail Gorbachev at a Summit meeting Geneva 1985 The experiment is jointly funded by China, Europe, India, Japan, Korea, Russia and the US representing more than half the population of the world

3. What is Nuclear Fusion? Nuclear fusion is the reaction between two nuclei to form a larger one. When the mass of the product nucleus is less than the mass of the two original nuclei the excess mass is released as energy » + 4 MeV + 3.3 MeV + 17.6 MeV Key reaction + 18.3 MeV

4. Nuclear Fusion Power Plants Assuming that the problem of plasma confinement would be solved the design of fusion power plants was considered very early in the international fusion program A patent for a fusion power plant was filed in 1946 by GP Thomson and M Blackman of Imperial college London. In the 1950’s Lyman Spitzer at Princeton NJ considered the design of a fusion reactor In the late 1960’s after the success of the Soviet tokamaks there were many attempts to design tokamak reactors, particularly in the US and the UK

5. Conceptual fusion reactor

6. Attempts to produce fusion power on earth Fusion reaction occur in the sun because gravity holds the reacting particles close enough together for the reaction to occur On earth man first succeeded in producing the reaction in the hydrogen bomb in 1952 This destructive approach is of no use for generating useful power Instead we have tried to produce the reaction in a controlled manner by using magnetic and electric fields. Experiments started in the late 1940’s and have continued to the present day. Early successes were the Soviet tokamaks (1960’s) The first demonstration of controlled DT fusion reactions was in 1991 on the European tokamak JET. About 1 MW was produced for aver 1 second

7. Tokamak Principles Confinement is produced by the combination of toroidal field produced by external coils and a poloidal field produced by a current in the plasma

8. Experimental fusion power production JET and TFTR have demonstrated fusion reactions. The maximum power achieved was 16 MW The value of Q=Power out/power in =0.6 Q in ITER is planned to be 10

9. The INTOR programme INTOR was the first international attempt to design a fusion reactor In the late 1970’s 3 large tokamaks were being designed JET, TFTR and JT60 IAEA proposed a workshop in Vienna with US, USSR, JA and EU This defined a reactor design with S/C magnets, T breeding, remote handling and materials testing, 1980 DESIGN had R=5m, a=1.2m I p =8-10 MA

10. Scaling confinement time from experiments to ITER

11. Origins of ITER Velikhov, Gorbachev and Mitterand Regan -Gorbachev summit, Geneva Nov 1985 Japan and Europe invited to join a 4 party programme to build a reactor IAEA invitation to Vienna workshop March 1987. Report produced and Joint Working site at Garching(Germany) agreed

12. President Reagan, Gorbachev Geneva Summit, 1985

13. Designing ITER Conceptual design 1988-90 Engineering design 1992-94 (Rebut) Engineering design 1994-98 (Aymar) Redesign 1998-2001 (Aymar)

14. Problems over siting design team 3 sites proposed Japan Naka(External components) Europe Garching, Germany (Internal comp.) USA San Diego (Integration) Three joint sites agreed. This led to a complicated structure and a lot of travelling

15. Engineering Design 1992-94 Director Paul-Henri Rebut (centre) Deputy directors(from left) Valery Chuyanov (RF), Michel Huguet (EU) Ron Parker (US), Yasuo Shimomura (JA)

16. Robert Aymar Director (1994-2003)

17. Comparison of JET and ITER JET R=3m Ip=4MA ITER R=6.2m Ip=15MA JET is the largest presently existing tokamak

18. The 2001 ITER design Toroidal Field Coil Nb 3 Sn, 18, wedged Central Solenoid Nb 3 Sn, 6 modules Poloidal Field Coil Nb-Ti, 6 Vacuum Vessel 9 sectors Port Plug heating/current drive, test blankets limiters/RH diagnostics Cryostat 24 m high x 28 m dia. Major plasma radius 6.2 m Plasma Volume: 840 m 3 Plasma Current: 15 MA Typical Density: 10 20 m -3 Typical Temperature: 20 keV Fusion Power: 500 MW Machine mass: 23350 t (cryostat + VV + magnets) - shielding, divertor and manifolds: 7945 t + 1060 port plugs - magnet systems: 10150 t; cryostat: 820 t

19. Seven Large Projects to study manufacturing Central solenoid coil (Nb/Sn S/C) L1 Toroidal field coil (Nb/Sn S/C) L2 Sector of the vacuum vessel L3 Blanket module L4 Divertor cassette L5 Blanket remote handling system L6 Divertor remote handling system L7

20. Magnets and Structures S uperconducting. 4 main subsystems: 18 toroidal field (TF) coils produce confining/stabilizing toroidal field; 6 poloidal field (PF) coils position and shape plasma; a central solenoid (CS) coil induces current in the plasma. correction coils (CC) correct error fields due to manufacturing/assembly imperfections, and stabilize the plasma against resistive wall modes.

21. Vessel, Blanket and divertor The double-walled vacuum vessel is lined by modular removable components, including blanket modules, divertor cassettes, and diagnostics sensors, as well as port plugs for limiters, heating antennae, diagnostics and test blanket modules. All these removable components are mechanically attached to the VV. The total vessel/in-vessel mass is ~10,000 t. These components absorb most of the radiated heat from the plasma and protect the magnet coils from excessive nuclear radiation. The shielding is steel and water, the latter removing heat from absorbed neutrons. A tight fitting configuration of the VV to the plasma aids passive plasma vertical stability, and ferromagnetic material “inserts” in the VV located in the shadow of the TF coils reduce toroidal field ripple and its associated particle losses.

22. Safety and Environmental Characteristics ITER will be a precedent for future fusion licensing Work towards internationally accepted basic principles and safety criteria for fusion energy Interact with regulatory experts to ensure ITER options can be licensed in any Party

23. Parameters of the ITER designs The Rebut design in 1994 had 24 field coils but was otherwise similar to the 1998 design

24. Political aspects 1998-2001 US withdrawal, no site offered June 2001, Canadian site proposed June 2002 JA offers Rokkasho, EU offers Caderache and Vandellos -- now 4 sites! EU withdraws Vandellos, CA withdraws Jan 2003 China joins, US rejoins, KO joins Washington meeting to decide site ends in stalemate 2003-2006 Battle between EU and JA for site Proposal for a broader approach Agreement on the Caderache site

25. Signing the treaty, Paris, 21 November 2006

26. The ITER buildings today Cadarache, near Aix-en-Provence, France

27. ITER collaboration For its size and cost and the involvement of virtually all the most developed countries, representing over half of today world’s population ITER will become a new reference term for big science projects. The ITER project is one of the world’s biggest scientific collaboration.

28. The ITER organization

29. ITER Director-General Dr Kaname Ikeda (Japan)

30. Deputy Director General and Project construction leader Dr Norbert Holtkamp EU

31. Deputy Director Generals Valery Chuyanov RF Fusion Science Gary Johnson US Tokamak Carlos Alhedre EU Safety, Environment Dhijaj Bora (IN) Control Diagnostics and Heating Kim KO, Engineering, Fuel cycle Wang CN Administration, Finance

32. Proposed ITER Site Layout

33. Staff Planning

34. Indicative Construction Schedule

35. Indicative Operation Schedule

36. Why is ITER important? Features Virtually inexhaustible power No CO 2 emissions High energy density fuel –1 gram D-T = 26000 kW·hr of electricity (~10 Tonnes of Coal !!) Inherently Safe Controllability –low fuel inventory, ease of burn termination, self-limiting power level –No chain reaction to control –low power and energy densities, large heat transfer surfaces and heat sinks Issues Fusion reaction is difficult to start and maintain –High temperatures (Millions of degrees) required –Technically complex & LARGE devices are required

37. The Broader Approach During the JA-EU discussions over ITER site a “Broader Approach” was suggested. This now has 3 parts –International Fusion Irradiation Facility (IFMIF) –International Fusion Research Centre –Advanced S/C tokamak at Naka Japan The research centre will work on DEMO

38. Provisional future programme

39. Project Schedule (2006) 20052006200720082009201020112012201320142015 ITER IO LICENSE TO CONSTRUCT TOKAMAK ASSEMBLY STARTS Bid Contract EXCAVATE TOKAMAK BUILDING OTHER BUILDINGS TOKAMAK ASSEMBLY COMMISSIONING MAGNET VESSEL Bid Vendor’s Design Bid Install cryostat First sector Complete VV Complete blanket/divertor PFC Install CS First sectorLast sector Last CSLast TFC CSPFCTFC fabrication start Contract 2016 Construction License Process

40. The ITER site Tokamak building Tritium building Cryoplant buildings Magnet power convertors buildings Cooling towers The Hot cell The site will cover about 60 ha, with buildings over 170m long