Structural Materials for Magnetic Confinement Fusion Reactorsweb.luli.polytechnique.fr/IFE-KiT/Techno_watch/220310_Gonzalez.pdf · steels focus on the development of materials combining

Technology watch workshop on IFE-KiT, 22 March, 2010, Madrid, Spain1

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Structural Materials for Magnetic Structural Materials for Magnetic Confinement Fusion ReactorsConfinement Fusion Reactors

SehilaSehila M. M. GonzálezGonzález de Vicentede VicenteMaterials R.O.Materials R.O.

EFDAEFDA--GarchingGarching CSUCSU


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OutlineOutline•• Introduction: Inertial/Magnetic Confinement FusionIntroduction: Inertial/Magnetic Confinement Fusion•• Structural Materials in Magnetic Confinement Fusion:Structural Materials in Magnetic Confinement Fusion:

–– Fusion Materials Topical Group (FMTG)Fusion Materials Topical Group (FMTG)• ODS FS• W and W alloys• SiC/SiC

–– F4EF4E• EUROFER• EUROFER ODS

•• A dedicated fusion test facility: IFMIFA dedicated fusion test facility: IFMIF•• SummarySummary


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2018

Inertial/Magnetic: in size, very similarInertial/Magnetic: in size, very similar……


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Neutron flux and Neutron flux and fluencefluenceDisplacement damage Displacement damage ⇒⇒ affects ALL materialsaffects ALL materials

• MC (ITER etc.)

First wall ≈ 10 19 n/m2/sduring ≥ 1000 s

i.e. ≈ 10-6 dpa/s

⇒ 300 h operation ≈ 1 dpa !

"rule of thumb" 1025n/m2 => 1 dpa (displacement per atom)

• IC (LMJ etc.)

First wall ≤ 3x10 16 n/m2/shotduring < 300 ns

only 3x10-9 dpa/shotBUT ≡ 10-2 dpa/s

For 50 shots/s=> 300 h operation ≈ 0.2 dpa

……but not in operating conditionsbut not in operating conditions


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Agency MissionEFDA Divertor & long-term activities

(“new materials” or “high risk development”)• Ferritic ODS steels.• Tungsten (alloy) development.• SiC/SiC composites for struct. Application.• Radiation effect modelling and validation

Fusion for Energy (F4E)

Materials for Breeding Blankets (BB)TBM (and DEMO) relevant activities EUROFER-97: Production and QualificationFuture R&D: RAFM steels for BBEUROFER ODS

EU supervision of Broader Approach

(A simple picture of the)(A simple picture of the)OrganisationOrganisation of theof the EU Materials DevelopmentEU Materials Development

Courtesy of E. Diegele (F4E)


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FUSION MATERIALS TOPICAL FUSION MATERIALS TOPICAL GROUPGROUP

•• MATMAT--REMEV: REMEV: Radiation Effects Modelling and Experimental Radiation Effects Modelling and Experimental ValidationValidation

-- Develop Physically based Develop Physically based ModellingModelling Tools + ValidationTools + Validation-- Provide guidance for Provide guidance for optimisingoptimising the IFMIF test the IFMIF test programmeprogramme..

•• MATMAT--ODSFS: ODSFS: NanoNano--structured ODS structured ODS FerriticFerritic Steel DevelopmentSteel Development-- NanoNano--structured ODS RAF steels: development + fabrication + characterstructured ODS RAF steels: development + fabrication + characterizationization

•• MATMAT--W&WALLOYS: W&WALLOYS: Tungsten and Tungsten Alloys DevelopmentTungsten and Tungsten Alloys Development--Development of Structural + Armour Tungsten MaterialsDevelopment of Structural + Armour Tungsten Materials

•• MATMAT--SiC/SiCSiC/SiC: : SiCf/SiCSiCf/SiC Composite for Structural Application in Fusion Composite for Structural Application in Fusion ReactorReactor

- Processing techniques for manufacturing SiCf/SiCProcessing techniques for manufacturing SiCf/SiC--Increase in thermal conductivityIncrease in thermal conductivity


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MATMAT--ODSFSODSFSNanoNano--structured ODS structured ODS FerriticFerritic

Steel DevelopmentSteel Development


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ODS RAF ODS RAF SteelsSteels: P: Pootentialtential ApplicationsApplications

• Plate supporting the W tiles in the European dual-coolant lithium-lead (DCLL) breeding blanket concept

• Cartridge within the finger- like units of the European He-cooled divertor concept

DEMO ~ 100 dpa


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PerspectivesPerspectives

? - 650°C

Nano-clusters: smaller,more complex chemical composition, different

orientation relationship with the matrix ?

350°C - 550°C

RAFM steels ODS RAFM steels

? - 750°C

ODS RAF steels

Small oxides

••Europe, Japan, and the US are actively researching steels with hEurope, Japan, and the US are actively researching steels with high igh tensile and creep strength at higher temperatures and sufficienttensile and creep strength at higher temperatures and sufficient ductility ductility and fracture toughness at low and intermediate temperaturesand fracture toughness at low and intermediate temperatures••The numerous interfaces between the matrix and the oxide particlThe numerous interfaces between the matrix and the oxide particles and es and between the grains are expected to act as sinks for the irradiatbetween the grains are expected to act as sinks for the irradiationion--induced induced defectsdefects


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ODSFS STATUSODSFS STATUS

• European activities in the field of ODS RAF steels focus on the development of materials combining – Isotropic microstructure = isotropic properties– High tensile and creep strength at elevated Ts– Reasonable ductility and fracture toughness at low and

intermediate Ts– Good radiation resistance under fusion power reactor irradiation

conditions

• This approach should yield the industrial fabrication of an optimized ODS RAF steel in about five years


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MATMAT--W&WALLOYSW&WALLOYSTungsten and Tungsten Alloys Tungsten and Tungsten Alloys

DevelopmentDevelopment


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W & W-Alloys for Armour & Structure:He-cooled Divertor Concept for DEMO

W tileW tile:: max. allow temp. 2500°C max. calc. temp. 1711°C

DBTT (irr.): 700°C

Thimble:Thimble: max. allow. temp. 1300°Cmax. calc. temp. 1170°C

DBTT (irr.): 600°C

ODSODS--Eurofer:Eurofer: He-out temp. 700°CHe-in temp. 600°C

DBTT (irr.): 300°C

10 MW/m2 Heat Flux Fatigue Testing

~10 MW/m2 ~100 cycles

Infra-Red Image during testing

P. Norajitra et al., FZK


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Helium cooled DEMO Divertor: Challenges

• Materials Development– Structural Materials (Ductility, Thermal Conductivity, Grain Growth)– Armor Materials (Crack & Oxidation Resistivity) – Large Scale Production

• Manufacturing– Fabrication, Mass/Series Production– Joining (Brazing, Grading)

– Mock-up HighHeat Flux Testing

• Irradiation Damage– Embrittlement, Hardening, etc.– Transmutation/Helium Production– Tritium Retention


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W & W alloys STATUSW & W alloys STATUS

• The most critical part of the programme is the development of a material for structural divertor parts: ductile within the operation temperature range

• Joining of tungsten materials is possible, but developing low-activation brazing materials is still a problem

• Testing and characterizing possible armor materials is well advanced and may lead to optimized armor materials


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MATMAT--SiC/SiCSiC/SiCSiCf/SiCSiCf/SiC Composite for Composite for

Structural Application in Fusion Structural Application in Fusion ReactorReactor


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SiCSiC//SiCSiC CompositesComposites forfor SStructuraltructural AApplicationpplication

High residual porosity for the most developedprocessing route (CVI)

SiC fibres sensitive at high T processing

Sintering additive are needed for densification

Porosity and oxide impurities lower the λ

β-SiC transforms to α-SiC at high temperatures

ISSUESMAIN REQUIREMENTS

Non-porous (gas impermeability) …………….

High mechanical strength and reliability……

Low neutron activation …………………..

High thermal conductivity ……………………….

No (low) swelling …………………………………..

Elimination / lowering porosity alternative processing technique

Increase in thermal conductivity lower porosity + incorporation ofmaterials with higher λ (e.g. metal)

OBJECTIVES


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EUROFER EUROFER -- SummarySummary

• Three large industrial heats of EUROFER have been produced and characterised in unirradiated and irradiation campaigns up to 70 dpa.

• For sound and valid characterization programme, EUROFER-97 is selected as reference for TBM.

• Current R&D activities focus on the completion of the data base for TBM design and licensing.

• Scope: Data base should be completed within ~5 years (un-irradiated) for final design, < 10 years (for

licensing).• Evidence that TBM can be successfully fabricated and tested

in ITER.

17Courtesy of E. Diegele (F4E)


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EUROFER for EUROFER for DEMO BBDEMO BB


AdvantagesGood balance of properties.Well-know fabrication technology. Various options for joining. Significant data base to start immediate CDA (conceptual design).

Issues & LimitationsEmbrittlement at low T and high dose. Limited to ~(300)/350-550°C (#).

Concern: Effects of (additional) transmutational helium

Evidence that material is suitable for a first DEMO BB (~30-50dpa) .To be confirmed for base materials and welds. Further potential to be evaluated. [No fundamental issues for exclusion.]

(#)Caution: This does not mean that the material cannot be used below 300 °C or above 550°C and 50 dpa. Lifetime depends on T, dose & loading (operational conditions).


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EUROFER ODS Steel EUROFER ODS Steel 9Cr9Cr--1W Ta V + 0.3% Y1W Ta V + 0.3% Y22OO33

AdvantagesGood high T strength (creep, tensile, creep-fatigue). Indications for higher irradiation resistance and improved tolerance against Helium. Nano-structure (nano grains and nano-dispersoides Y2O3, Y2Ti2O7).

Strengthen the material without loss of ductility.Act as re-combination centers (sinks) for irradiation induced defects. Suppress embrittlement.

Issues & LimitationsReduced fracture toughness & higher DBTT.Scalability of fabrication process (from “kg” to “tons”).Few options for joining (“non-melting”: diffusion bond, stir friction).(Currently lack of industrial partners in the EU).

Application: EUROFER ODS is not foreseen to replace RAFM steels 1-by-1,

rather than to complement EUROFER.Fabrication of a full BB box questionable (would need different design approach &

fabrication).[ Temperature window: 350/400(?)-650°C]



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Fusion Fusion –– dedicated test Facility: dedicated test Facility: IFMIFIFMIF


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IFMIF: International Fusion Material IFMIF: International Fusion Material Irradiation FacilityIrradiation Facility

• IFMIF Motivation:– At present there is no entirely suitable Irradiation Test

Facility for materials in a suitable representative “FUSION environment“.

– Urgent need not only for R&D of new technologies but also for licensing of existing ones.

– International Fusion community has made an effort to find the best available fusion source to develop Fusion devices beyond


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Intense source of 14 MeV neutrons (250 mA D+): the neutron spectrumshould meet the first wall neutron spectrum as near as possible.Missions:• Qualification of candidate materials up to about full lifetime of anticipated use

in a fusion DEMO reactor• Calibration and validation of data generated from fission reactors and particle

accelerators• Identify possible new phenomena which might occur due to the high energy

neutron exposure

What is IFMIF?What is IFMIF?

IFMIF ProjectIFMIF Project• High power (10MW), huge flux (20 to 50 dpa/fpy) & high energy neutron

source• Will test technologies beyond ITER.• The IFMIF programme foresees 2 phases:

- Engineering Validation, Engineering Design Activities (EVEDA). Duration: 6 years.- Construction Phase: 7 years.

• Started in 2007.• Many challenges: Requirements & reliability.


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FeaturesFeatures

0 20 40m

Ion SourceRFQ

Li Target

High Energy BeamTransport

Li Loop

Test modules insideTest Cell

PIE Facilities

Peak is centredat 14 MeV

But even with thissource, neutronspectrum is notperfect.

40-50~ 800≤ 1040-50Hydrogen[appm/dpa]

10-12~ 130≤ 110-15Helium[appm/dpa]

20-55~ 10~ 2020-30Damage rate [dpa/year]

IFMIF(High flux module)

High energyprotons

(590 MeV)

Fission neutrons(BOR 60 reactor)

Fusion neutrons(3-4 GW reactor, first wall)

Defectpoduction(in steels)


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SummarySummary•• Introduction: Inertial/Magnetic Confinement FusionIntroduction: Inertial/Magnetic Confinement Fusion

–– Same size devices, but different operation condition Same size devices, but different operation condition →→ different level of different level of DAMAGEDAMAGE

•• Structural Materials in Magnetic Confinement FusionStructural Materials in Magnetic Confinement Fusion–– Fusion Materials Topical Group (FMTG): Fusion Materials Topical Group (FMTG): Not mature enough Not mature enough →→ linked to

DEMO design•• ODS FS:ODS FS: main goal →→ industrial fabrication of an optimized ODS

RAF steel in about five years, up to 750°C•• W and W alloys:W and W alloys: armor (cracks formation) + structural (ductility)•• SiC/SiCSiC/SiC:: porosity + thermal conductivity

–– F4E: matured enough F4E: matured enough →→ mostly to be used in ITERmostly to be used in ITER•• EUROFER:EUROFER: EUROFER-97 is selected as reference for TBM, 300-

550 °C•• EUROFER ODS:EUROFER ODS: to complement EUROFER, up to 650°C

•• A dedicated fusion test facility: IFMIFA dedicated fusion test facility: IFMIF–– First wall neutron spectrum: Qualification of candidate materialFirst wall neutron spectrum: Qualification of candidate materials + s +

Calibration and validation of data + Identify possible new phenoCalibration and validation of data + Identify possible new phenomena mena


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Thank you very much for your Thank you very much for your AttentionAttention


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Inertial confinement Inertial confinement -- pulsed radiationpulsed radiation

• Implode small capsules containing D and T

• Use lasers or ion beams

Nova laser system LLNL

• Ambitious near term plans• NIF (US) and LMJ (F)

National Ignition Facility

Documents

Structural Materials for Magnetic Confinement Fusion Reactorsweb.luli.polytechnique.fr/IFE-KiT/Techno_watch/220310_Gonzalez.pdf · steels focus on the development of materials combining