Nuclear Energy in the Future. The ITER Project. Brad Nelson. Chief Engineer, US ITER. Presentation for NE-50 Symposium on the Future of Nuclear Energy

Transcription

1 Nuclear Energy in the Future The ITER Project Brad Nelson Chief Engineer, US ITER Presentation for NE-50 Symposium on the Future of Nuclear Energy November 1, 2012

2 Fusion research is ready for the next step A self-heated burning Plasma 2

3 We Have Produced Fusion Power 3

4 Joint European Torus (JET) is largest existing tokamak, <16 MW fusion power out, ~ 25 MW in ~15 m JET 4

5 The next step is ITER: 500 MW fusion power, gain (Q) of 10 ~29 m R=6.2 m, a=2.0 m, I p =15 MA, B T =5.3 T, 23,000 tons ~15 m JET 5 ITER

6 Fusion has made steady progress, ITER goal is a big step 11/1/2012 6

7 ITER is a special partnership to address a global challenge and opportunity Partnership: a unique arrangement of nations jointly responsible for construction, operation, and decommissioning Mission: to demonstrate the scientific and technological feasibility of fusion energy 7

8 The Signatories of the ITER Agreement Elysée Palace, Paris: November 21, 2006 with French President Jacques Chirac, in Paris, France, on November 21, From left to right: Vladimir Travin (Deputy Director of the Federal Atomic Energy Agency, Russian Federation), Kim Woo Sik (Vice Prime-Minister, Ministry of Science and Technology, Korea), Takeshi Iwaya (Vice-Minister for Foreign Affairs, Japan), José Manuel Barroso (President of the European Commission), Jacques Chirac (President of the French Republic), Xu Guanhua (Minister of Science and Technology, People's Republic of China), Anil Kakodhar (Secretary to the Government of India, Department of Atomic Energy), Dr. Raymond Orbach (Under Secretary for Science, U.S. Department of Energy), and Janez Potočnik (European Commissioner for Science and Research). 8

9 Negotiated Value Proposition Benefit Sharing Equal access to data Right to propose and conduct experiments Participation in design and access to design information U.S. industry role in manufacturing hightechnology components Joint ownership of intellectual property Cost Sharing (mostly in-kind) 9

10 ITER site is in France 10

11 ITER site is in France 11

12 The ITER Site Plan shows ITER scope Birdseye View of the ITER Site Will cover about 60 ha (150 acres) Large number of systems Cooling Towers (1200 MW) Tokamak / Assy Buildings 2x750 ton cranes 170 m long Hot Cell PF Assy Building Magnet Power Convertor Buildings (500 MW Pulsed) Cryoplant Building (85 4.5k,

13 The ITER Site Plan shows ITER scope Birdseye View of the ITER Site Will cover about 60 ha (150 acres) Large number of systems Cooling Towers (1200 MW) Tokamak / Assy Buildings 2x750 ton cranes 170 m long Hot Cell PF Assy Building Magnet Power Convertor Buildings (500 MW Pulsed) Cryoplant Building (85 4.5k,

14 ITER Today construction in progress NE 50 ITER Photos by ITER organization

15 ITER Today construction in progress NE 50 ITER Photos by ITER organization

16 ITER Today construction in progress NE 50 ITER Photos by ITER organization

17 ITER Today construction in progress NE 50 ITER Photos by ITER organization

18 ITER Today construction in progress NE 50 ITER Photos by ITER organization

19 ITER Today construction in progress NE 50 ITER Photos by ITER organization

20 ITER Tokamak Building Defined by Levels L5 L4 L3 L2 L1 B1 B2 Seismic bearing pedestals 20

21 ITER Tokamak Core in Building 9/18/

22 ITER Level 0 Construction Schedule First Plasma November 2020 ~20 years operation First plasma 22

23 ITER has many engineering challenges How do we: Provide specified magnetic field over a large volume? Protect the device from high heat flux and neutrons? Heat the plasma and drive the plasma current? Diagnose the plasma? Fuel the plasma? Maintain the device over time? 23

24 The Core of ITER 24

25 ITER s Magnet System Toroidal field (TF) coils produce confining/ stabilizing toroidal field Poloidal field (PF) coils position and shape plasma Central solenoid (CS) coil induces current in the plasma Magnet System weighs ~ 8,700 tons (same as frigate USS Bainbridge) NE 50 ITER 25

26 Magnets are unprecedented in size and performance for fusion systems 40 mm dia TF coils 11.8 Tesla, 41 GJ 40,000 tons centering force NE 50 ITER 11/1/

27 Magnets are unprecedented in size and performance for fusion systems TF conductor close-up 40 mm dia TF conductor, as formed into pancakes NE 50 ITER 11/1/

28 TF conductor is being delivered Over 70% of required 450t of Nb 3 Sn strand has been produced around the world 28

29 TF coils are being constructed now A1 Segment TF Coil ~360 t, 16 m Tall x 9 m Wide B3 Segment 29

30 Magnets are unprecedented in size and performance for fusion systems Central Solenoid 13 Tesla, 7 GJ 30 kv, 1.2 T/s 6 coil modules in stack 30

31 Magnets are unprecedented in size and performance for fusion systems Single CS module, 553 turns Central Solenoid 13 Tesla, 7 GJ 30 kv, 1.2 T/s 6 coil modules in stack 31

32 Central Solenoid Conductor Nb 3 Sn cable in conduit 45 ka max current at ~13T > 40 km finished conductor required Insulation wrapping machine Conductor forming trials CS conductor with cabling exposed 32

33 Inside the magnet set are the vacuum vessel and in-vessel components Vacuum Vessel 9 sectors Toroidal Field Coil Blanket 440 modules Poloidal Field Coils Divertor 54 cassettes 33

34 Vacuum vessel is the plasma chamber Double walled, water-cooled, stainless steel structure provides high quality vacuum and first confinement barrier for radioactive materials. Prototype constructed to prove feasibility of double wall construction with prototypic size and tolerances m 3 +/- 15 mm Vessel must be protected from the plasma. 34

35 Vacuum vessel is the plasma chamber Double walled, water-cooled, stainless steel structure provides high quality vacuum and first confinement barrier for radioactive materials. Prototype constructed to prove feasibility of double wall construction with prototypic size and tolerances m 3 +/- 15 mm Vessel must be protected from the plasma. 35

36 Plasma interacts with surfaces 36 Photos courtesy JET

37 Divertor Exhausts a Major Part of Plasma Heating Power and Helium Ash Divertor Cassette (upgradeable) Challenge: Absorb MW/m 2 heat flux while minimizing impurity influx, tritium retention 37

38 First Wall and Blanket Take Balance of Neutron Radiation and Plasma Heat Load The blanket serves three main functions: To remove the useful neutron power and most of the particle power in the plasma To provide shielding of the vacuum vessel structure and S/C coils To help in passive stabilization of the plasma 38

39 First Wall Plasma Heat Load requires special technology Ref: Raffray 39

40 Plasma Heating/Current Drive Require Multiple Systems 40

41 ~ 50 Diagnostics Monitor Plasma Behavior Must Survive Harsh Operating Conditions ITER relative to JET High neutron and gamma fluxes (up to x 10) Neutron heating (1 MW/m 3 ) (essentially zero) High fluxes of energetic neutral particles from CX (up to x5) Long pulse lengths (up to x 100) High neutron fluence (> 10 5! ) 41

42 42 Fueling of plasma by frozen pellets Pellet injection to achieve efficient core fueling Protium, Deuterium and Tritium 14 Kelvin

43 Test Blanket modules demonstrate tritium breeding technology 43 Tritium breeding is necessary for the fusion fuel cycle. Several breeding blanket concepts are under consideration. ITER provides three equatorial ports for test blanket modules.

44 Other challenges In addition to challenges already discussed (related to component performance requirements and design), there are global challenges. Availability issues Reliability issues Remote Maintenance issues Vacuum quality, leaks, and in-situ leak detection Safety and interaction with regulators 44

45 Blanket maintenance requires in-vessel rail and vehicle Maintenance system deployed through 4 ports, requires rail, vehicle, system to hand components from vehicle to port, etc. Larger-scale system built and tested in JA. Development of new system will include significant deployment and use during machine assembly. Demonstration of Blanket module handling Rail deployment 1 blanket in months, all in ~2 years 45

46 What ITER Means for the US Create, understand, and control a reactorprototypical fusion plasma Demonstrate the scientific and technological feasibility of a promising virtually inexhaustible and relatively clean energy source Position the US to provide fusion-reactor technology Create high-tech jobs and work in the US International partnership: working together toward a global goal. 46

47 US Scope is provided by multiple institutions ORNL 100% Central Solenoid Windings + JA Support ORNL 8% of Toroidal Field Conductor + JA Support ORNL 100% Pellet Injector 100% Disruption Mitigation PPPL 14% of Port-based Diagnostics ORNL 88% Ion Cyclotron Transmission Lines ORNL 88% Electron Cyclotron Transmission Lines ORNL Blanket/Shield (design only) PPPL In-Vessel Coils (prelim. design only) ORNL 100% Tokamak Cooling Water System ORNL 100% Roughing Pumps, Vacuum Standard Components PPPL 75% Steady State Electrical Network SRNL 100% Tokamak Exhaust Processing System NE 50 ITER 47

48 US Scope is highly integrated with central ITER core Cooling Water System Central Solenoid ECH Transmission Lines ICH Transmission Lines Vacuum System TEP TF Coil Conductor SSEN Port Diagnostics Blanket/Shield Design Pellet Injection System Disruption Mitigation 48

49 Over 80% of Project Funding will be Spent in the US As of June 2012, over $808M (in total value with options) has been awarded to US industry, universities, and DOE laboratories in 38 states plus DC. Note: This data does not reflect contracts Awarded to US Industry by the EU (>$55M) or Korea (>$23M) 49

50 Summary The ITER project combines the expertise from around the world to build the first fusion reactor China, EU, India, Japan, Korea, Russian Federation and the U.S. An international organization is already operating in Cadarache, France, where ITER is under construction. There are many engineering challenges, but each can be met. ITER is proceeding toward a first plasma in