Present Status of the World-wide Fusion Programme and possible applications of superconducting...

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The International Workshop on Thin Films. Padova 9-12 Oct. 2006 1 of slides Present Status of the Present Status of the World-wide Fusion World-wide Fusion Programme and possible Programme and possible applications of applications of superconducting superconducting Accelerators Accelerators . . Roberto Andreani

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Present Status of the World-wide Fusion Programme and possible applications of superconducting Accelerators . Roberto Andreani. What is fusion?. Why Fusion?. The Magnetic Confinement. Fusion: a Breeding Reactor. JET. From JET to ITER. 500 MW,400s,Q = 10. 16 MW power produced. 1s. - PowerPoint PPT Presentation

Transcript of Present Status of the World-wide Fusion Programme and possible applications of superconducting...

Page 1: Present Status of the World-wide Fusion Programme and possible applications of superconducting Accelerators .

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Present Status of the World-Present Status of the World-wide Fusion Programme and wide Fusion Programme and

possible applications of possible applications of superconducting Acceleratorssuperconducting Accelerators..

Roberto Andreani

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What is fusion?What is fusion?

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Why Fusion?Why Fusion?

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The Magnetic ConfinementThe Magnetic Confinement

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Fusion: a Breeding ReactorFusion: a Breeding Reactor

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JETJET

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From JET to ITERFrom JET to ITER16 MW power produced. 1s

500 MW,400s,Q = 10

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Progress in fusion physics Progress in fusion physics understandingunderstanding

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Major Technological Problems of Major Technological Problems of ITERITER

• Superconducting Magnets (Nb3Sn);

• Plasma Facing components (Be→W);

• Remote Handling;

• Structural Materials (St.St.→Martensitic).

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Interaction of 14 MeV neutrons with Interaction of 14 MeV neutrons with the structural materialsthe structural materials

• Atoms displacement from their positions in the lattice→ Hardening and brittleness.1 MW/m2a = 10 dpa.Reactor first wall: ~ 2 MW/m2 → 20 dpa/a

• Transmutation reactions: Hydrogen and helium produced→Swelling and brittleness.

• A cumulative effect is the change in the Ductile to Brittle Transition Temperature (DBTT).

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Displacement in the DBTT. Displacement in the DBTT. ((Measured after irradiations in fission Measured after irradiations in fission

reactors)reactors)

0

1

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-180 -150 -120 -90 -60 -30 0 30 60 90 120 150 180 210Temperature (°C)

Impa

ct E

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y (J

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Eurofer Bar/8/14mm plate

BS-Eurofer plate 25 mm

BS-Eurofer plate 25 mm2.7 dpa 60°CF82H plate 9741 15 mm

F82H plate 9741 15 mm2.1 dpa 60°CF82H plate 9741 15 mm2.5 dpa 300°C

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IFMIF (International Fusion Materials IFMIF (International Fusion Materials Irradiation facility)Irradiation facility)

• An intense source of 14 MeV neutrons (1018 n/s). 50 dpa/a in 0.5 l volume. 20 dpa/a in 6 l.

• To study the effect of 14 MeV neutrons on fusion reactor materials.

• So far only <1012n/s, 14 MeV sources available. Only qualitative probing of the effects of 14 Mev neutrons on materials possible.

• IFMIF experimentation, besides direct results, will also allow correlating the large amount of existing data collected in irradiations with fission neutrons or ion beams.

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IFMIFIFMIF

Ion Source RFQ

High-Energy Beam Transport

Li Target

Li Loop

Test Modules Inside Test Cell

PIE Facilities

0 20 40 m

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IFMIF. Target System.IFMIF. Target System.Schematic viewSchematic view

Mission:Obtain stable and high speed Li flow during 10 MW D+ beam loading

D+ Accelerator

Liquid Li Target

Neutrons(~1017n/s)Li Free

Surface

EMP

D+ Beam (10MW)

Specimens

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IFMIF Time Schedule and CostIFMIF Time Schedule and Cost• The IFMIF programme foresees two phases:

- Engineering Validation, Engineering Design Activities (EVEDA). Duration: 6 years.

- Construction Phase: 7 years.• EU is entering the EVEDA phase in the framework

of an Agreement of collaboration with Japan.• Cost of the EVEDA phase: 150 MEuro ( 65 % EU,

35 % Japan)• Estimated Cost of the Construction Phase:

800 MEuro. (In the framework of an international collaboration yet to be established)

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IFMIF NC AcceleratorsIFMIF NC Accelerators

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Main NC Accelerator CharacteristicsMain NC Accelerator Characteristics• ECR Ion Source, D+ 95 KeV, 140 mA.• Low Energy Beam transport.• Three sections 4-vanes RFQ: 95 KeV to 5 MeV,

125 mA.• Matching Section.• 10 Alvarez type DTL tanks: 5 MeV to 40 MeV,

125 mA. Length: 30.3 m: ave.: 1.15 MV/m.• Beam Centroid (20x5 cm cross section): Time

Averaged Position Tolerance on Target: ± 1 mm• 12-13, 1 MW, cw, 175 MHz RF Generators• 18.5 MW electric power from the network

required to power each accelerator.

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IFMIFAccelerator SystemIFMIFAccelerator System BaselineBaseline

RF Power System12 Required, 1MW CW, 175 MHz

High Energy Beam Transport (HEBT)

Drift Tube Linac (DTL)CW 175 MHz, 10 Tanks, 30.3 m, 40MeV

Matching Section (MS)2-single Gap Cavities, 4 Quadrupoles, 0.66 m long

Radio Frequency Quadrupole (RFQ)CW 175 MHz, 12.5 m long, water cooled, 5 MeV

Ion Injector CW ECR, Source, 140 mA D+, 95 keV, Magnetic LEBT to RFQ

Large Bore Quad & Dipoles, 55 meters long

Realization of stable steady operation: lifetime: 1,000hr。

Stable operation

Contact-free beam diagnostic technology

Availability>8 8 %

Hands-on  maintenance

Shaping beam footprint

Accelerator

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Choice of AcceleratorChoice of Accelerator• Within the end of the year an investigation will be conducted to

establish whether a solution with two accelerators, including superconducting DTLs, would offer definite advantages for IFMIF.

• For the normal conducting design:

- ECR ion source, D+ beam.

- nc RFQ, 5 MeV. Fed by ~ 1.6 MW RF power, 175MHz.

- The nc DTLs, 5 to 40 MeV, absorb: 10x710 kW RF power= 7.1 MW.

- Total RF power: 8.7 MW. ~ 18.6 MW from network.

- Length of the DTLs: 30.3 m.

• Beam power: 0.125 A x 40 MeV = 5 MW

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• A preliminary superconducting design has been considered:A preliminary superconducting design has been considered:

-- ECR ion source and nc RFQ are the same as for the nc ECR ion source and nc RFQ are the same as for the nc solutionsolution

-- one nc DTL, 5 to 10 MeV. Fed by one nc DTL, 5 to 10 MeV. Fed by ~ 0.7 MW RF power.~ 0.7 MW RF power.

-- 7 sc DTL, Nb at 4.2 K, 10 to 40 MeV. (1x700 + 6x450) kW = 7 sc DTL, Nb at 4.2 K, 10 to 40 MeV. (1x700 + 6x450) kW = 3.4 MW RF power.3.4 MW RF power.

-- Total RF power: 5.7 MW. Total RF power: 5.7 MW. ~11.4~11.4 MW from network. MW from network.

-- Length of the DTL: Length of the DTL: ~ 9~ 9 m. m.

-- Cryogenic power: ~ 700 W. Cryogenic power: ~ 700 W. 0.21 0.21 MW from the networkMW from the network

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SC DTL. (SC DTL. (PreliminaryPreliminary Conceptual design with Conceptual design with seven s/c cavities)seven s/c cavities)

Dia.= 1600 mmL = ~ 9 m

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Proposed Cross-Bar, H mode, Proposed Cross-Bar, H mode, superconducting cavity for IFMIFsuperconducting cavity for IFMIF

Diameter: 550 mm

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Qualitative Evaluation of the Qualitative Evaluation of the Superconducting Solution.Superconducting Solution.

• Advantages:- Maximum field gradient limited only by H in the superconducting walls and E max (potentially very good vacuum quality). No limitation due to cooling. Energy/m about 3 times . Length of the accelerator about 50%.- Capital cost saving:

- Linear Size of the building. But cryogenic system?- Number of RF generators.

- Operational costs. Overall electric energy from network.- Larger aperture of the drift tubes low wake fields, no

measurable impact on RF losses of the smaller shunt impedance lower activation (< 1 W/m beam loss needed).

• Disadvantages or doubts:- Cryogenic system, capital and operating cost. Space

requirement.- Time schedule for construction of the sc DTLs.- Reliability of the technology, to be assessed.- Maintenance problems. Access.

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Preliminary evaluations of the costs (to be assessed by an Ad Hoc WG). 20 years operation.

2 Accelerators(Complete)

Capital CostMEuro

Operating costsMEuro/year

NC solution 315 79

SC Solution 245 72

Saving 70 7