Japan considerations on design and qualification of PFC's for near term machines (ITER) Satoshi Suzuki 1, Satoshi Konishi 2 1 Japan Atomic Energy Agency.

Japan considerations on design aJapan considerations on design and qualification of PFC's nd qualification of PFC's

for near term machines (ITER)for near term machines (ITER)

Satoshi SuzukiSatoshi Suzuki11, Satoshi Konishi, Satoshi Konishi22

1 Japan Atomic Energy Agency1 Japan Atomic Energy Agency

2 Kyoto University2 Kyoto University

ContentsContents

Development / provisional procurement activity of Development / provisional procurement activity of the ITER divertor outer vertical targetthe ITER divertor outer vertical target Small divertor mock-upsSmall divertor mock-ups Non-destructive examination by using infrared Non-destructive examination by using infrared

thermographythermography

Development of the first wall of the ITER test Development of the first wall of the ITER test blanket module (TBM) blanket module (TBM) Provisional high heat flux test of the full-poloidal length Provisional high heat flux test of the full-poloidal length

TBM first wall mock-upTBM first wall mock-up

Development of the DEMO divertorDevelopment of the DEMO divertor Small divertor mock-ups made of ferritic steel with Small divertor mock-ups made of ferritic steel with

tungsten armortungsten armor

Development / provisional procurement activity of Development / provisional procurement activity of the the ITER divertor outer vertical targetITER divertor outer vertical target Small divertor mock-upsSmall divertor mock-ups Non-destructive examination by using infrared Non-destructive examination by using infrared

thermographythermography

Development of the first wall of the ITER test Development of the first wall of the ITER test blanket module (TBM) blanket module (TBM) Provisional high heat flux test of the full-poloidal length Provisional high heat flux test of the full-poloidal length

TBM first wall mock-upTBM first wall mock-up

Development of the DEMO divertorDevelopment of the DEMO divertor Small divertor mock-ups made of ferritic steel with Small divertor mock-ups made of ferritic steel with

tungsten armortungsten armor

ContentsContents

ITER Plasma Facing ComponentsITER Plasma Facing Components

Among the divertor high heat Among the divertor high heat flux components, JAEA is going to flux components, JAEA is going to procure all of the outer vertical procure all of the outer vertical targettarget 22 plasma facing units / 1 22 plasma facing units / 1

cassettecassette 54 cassettes + 6 spares54 cassettes + 6 spares

--> 1320 plasma facing units--> 1320 plasma facing units

Outer vertical target (JA)Outer vertical target (JA)

Inner vertical target (EU)Inner vertical target (EU)

Dome(RF)Dome(RF)

CassetteCassettebody (EU)body (EU)

Plasma

Tro

idal

coi

l

Divertor

First wall/Blanket

6.2m

Test Blanket Module(TBM)

Cross sectional view of ITERCross sectional view of ITER

ITER divertor

Outer vertical targetOuter vertical target Design heat fluxDesign heat flux

Tungsten part : 5MW/mTungsten part : 5MW/m22

CFC (Carbon Fiber Composite) CFC (Carbon Fiber Composite) part : 10 - part : 10 - 20MW/m20MW/m22

Coolant conditionCoolant condition Water, 4MPa, 100Water, 4MPa, 100ooCC Swirl flowSwirl flow by twisted tape (CFC by twisted tape (CFC

part)part) Bonding of armor materialsBonding of armor materials

BrazeBraze HIP (Hot Isostatic Pressing)HIP (Hot Isostatic Pressing)

Prior to the procurement of the Prior to the procurement of the vertical target components, the vertical target components, the manufacturing process and the manufacturing process and the thermal performance of the thermal performance of the components should be components should be validated/demonstrated by using small validated/demonstrated by using small mock-ups. ("Prequalification" activity)mock-ups. ("Prequalification" activity)

Tungsten

CFC

Tungsten

CFC

28mm

Soft copper

Copper alloyOuter vertical target (1 cassette)Outer vertical target (1 cassette)with "Monoblock" geometrywith "Monoblock" geometry

Optimization of the manufacturing Optimization of the manufacturing process by using small mock-upsprocess by using small mock-ups

Armor : CFC (CX-2002U)Armor : CFC (CX-2002U) Tube : CuCrZrTube : CuCrZr Bonding : Brazing (TBonding : Brazing (Tbrazebraze=980=980ooC)C)

Ni-Cu-MnNi-Cu-Mn Ti-Cu-NiTi-Cu-Ni

Metalizing of CFCMetalizing of CFC Present : Ti-Cu (5 - 10%-Ti)Present : Ti-Cu (5 - 10%-Ti)

Accuracy of machining of CFC Accuracy of machining of CFC holehole +/- 5 microns to the target +/- 5 microns to the target

valuevalue

High heat flux test has been High heat flux test has been performed to check the performed to check the soundness of the braze soundness of the braze interface and to demonstrate interface and to demonstrate the thermal performance.the thermal performance.

A small vertical target mock-A small vertical target mock-upupsimulating the CFC part of simulating the CFC part of the vertical targetthe vertical target

CFC

28mm

28mm

Soft Copper : 18/15mmCuCrZr tube : 15/12mm

High heat flux test of the small mock-High heat flux test of the small mock-upsups

and fabrication of a qualification and fabrication of a qualification prototypeprototype

Braze filler : Ni-Cu-Mn Braze filler : Ni-Cu-Mn (980(980ooC x 0.5h, followed by C x 0.5h, followed by Ar gas quench)Ar gas quench)

Metalizing : Present (Ti-Cu, Metalizing : Present (Ti-Cu, 7.5 - 10%-Ti)7.5 - 10%-Ti)

Aging : 475Aging : 475ooC x 2h C x 2h Finally, the mock-up Finally, the mock-up

fabricated by using fabricated by using parameters above could parameters above could withstand the heat flux of withstand the heat flux of 20MW/m20MW/m22 for 1000 cycles. for 1000 cycles.

at 5 MW/m2

(EB heating)

~500mm~500mm

CFCCFC

TungstenTungsten

ITER vertical targetITER vertical targetQualification PrototypeQualification Prototype

Based on the successful result of the Based on the successful result of the small mock-ups, a medium scale mock-small mock-ups, a medium scale mock-up (up (Qualification PrototypeQualification Prototype) has been ) has been manufactured. manufactured.

This mock-up includes most of the This mock-up includes most of the critical technical issues (bonding of critical technical issues (bonding of CFC/Cu, curved cooling tube, etc...) on CFC/Cu, curved cooling tube, etc...) on the fabrication of the ITER divertor the fabrication of the ITER divertor vertical target. This mock-up will be high vertical target. This mock-up will be high heat flux tested in Efremov institute in heat flux tested in Efremov institute in 2008.2008.

High heat flux test of the small mock-High heat flux test of the small mock-upsups

and fabrication of a qualification and fabrication of a qualification prototypeprototype

Braze filler : Ni-Cu-Mn Braze filler : Ni-Cu-Mn (980(980ooC x 0.5h, followed by C x 0.5h, followed by Ar gas quench)Ar gas quench)

Metalizing : Present (Ti-Cu, Metalizing : Present (Ti-Cu, 7.5 - 10%-Ti)7.5 - 10%-Ti)

Aging : 475Aging : 475ooC x 2h C x 2h Finally, the mock-up Finally, the mock-up

fabricated by using fabricated by using parameters above could parameters above could withstand the heat flux of withstand the heat flux of 20MW/m20MW/m22 for 1000 cycles. for 1000 cycles.

at 5 MW/m2

(EB heating)

~500mm~500mm

CFCCFC

TungstenTungsten

ITER vertical targetITER vertical targetQualification PrototypeQualification Prototype

The high heat flux test of the first mock-The high heat flux test of the first mock-up (VTQP-1) has been completed in up (VTQP-1) has been completed in November, 2008. This mock-up has November, 2008. This mock-up has successfully withstood the heat flux successfully withstood the heat flux requirements as follows;requirements as follows;

CFC : 10MW/mCFC : 10MW/m22 x 1000 + 20MW/m x 1000 + 20MW/m22 x x 1000cycles1000cycles

W : 3MW/mW : 3MW/m22 x 1000 + 5MW/m x 1000 + 5MW/m22 x 1000 x 1000 cyclescycles

Based on this, Japan Domestic Agency Based on this, Japan Domestic Agency (JADA) has been qualified to proceed the (JADA) has been qualified to proceed the subsequent divertor procurement.subsequent divertor procurement.

Development of a new NDE facilityDevelopment of a new NDE facility"FIND" ("FIND" (FFacility of acility of IInfrared nfrared NNon-on-

destructive examination for destructive examination for DDivertor)ivertor) In parallel to the optimization of the manufacturing process, In parallel to the optimization of the manufacturing process,

acceptance test methods have also been provided.acceptance test methods have also been provided. In addition to the conventional methods (UT, RT, He leak In addition to the conventional methods (UT, RT, He leak

testing for the braze/weld joint), infrared thermography testing for the braze/weld joint), infrared thermography examination is essential for the non-destructive examination of examination is essential for the non-destructive examination of the vertical target.the vertical target.

UT can detect the UT can detect the interfacial defects interfacial defects between CuCrZr between CuCrZr tube and soft tube and soft copper interlayer.copper interlayer.

CFC (porous)CFC (porous)

UT sensor

Internal defect of Internal defect of CFC or interfacial CFC or interfacial defect between defect between CFC and soft CFC and soft copper can not be copper can not be detected by UT.detected by UT.

CFC (porous)CFC (porous)

Development of a new NDE facilityDevelopment of a new NDE facility"FIND" ("FIND" (FFacility of acility of IInfrared nfrared NNon-on-

destructive examination for destructive examination for DDivertor)ivertor)

Development of a new NDE facilityDevelopment of a new NDE facility"FIND" ("FIND" (FFacility of acility of IInfrared nfrared NNon-on-

destructive examination for destructive examination for DDivertor)ivertor)

By monitoring of the thermal transient of the mock-ups due to By monitoring of the thermal transient of the mock-ups due to switching of the hot/cold water, internal defect of the CFC or switching of the hot/cold water, internal defect of the CFC or interfacial defect of the CFC/Cu joint can be detected.interfacial defect of the CFC/Cu joint can be detected.

Time-to-time differential of the thermal transient between defected Time-to-time differential of the thermal transient between defected and non-defected mock-ups gives quantitative evaluation of the and non-defected mock-ups gives quantitative evaluation of the defect size and the location with the help of FEM analysis.defect size and the location with the help of FEM analysis.

Development / provisional procurement activity of Development / provisional procurement activity of the ITER divertor outer vertical targetthe ITER divertor outer vertical target Small divertor mock-upsSmall divertor mock-ups Non-destructive examination by using infrared Non-destructive examination by using infrared

thermographythermography

Development of the first wall of the Development of the first wall of the ITER test ITER test blanket module (TBM)blanket module (TBM) Provisional high heat flux test of the full-poloidal length Provisional high heat flux test of the full-poloidal length

TBM first wall mock-upTBM first wall mock-up

Development of the DEMO divertorDevelopment of the DEMO divertor Small divertor mock-ups made of ferritic steel with Small divertor mock-ups made of ferritic steel with

tungsten armortungsten armor

ContentsContents

ITER TBM Test ProgramITER TBM Test Program ITER TBM Program is to test ITER TBM Program is to test the the

necessary functions of DEMO necessary functions of DEMO BlanketBlanket in the real fusion in the real fusion environment with test module environment with test module scalable to DEMO blanket.scalable to DEMO blanket. Demonstration of production of Demonstration of production of

fusion fuel tritiumfusion fuel tritium Demonstration of extraction of Demonstration of extraction of

energyenergy Demonstration of shielding Demonstration of shielding

performanceperformance ITER TBM Test Program is one of ITER TBM Test Program is one of

the most important development the most important development step.step.

Based on the results from the basic Based on the results from the basic R&Ds on material testing and R&Ds on material testing and fabrication trial, near-full-scale fabrication trial, near-full-scale mock-up has successfully been mock-up has successfully been developed.developed.

Plasma

Tro

idal

coi

l

Divertor

First wall/Blanket

6.2m

Test Blanket Module(TBM)

Cross sectional view of ITERCross sectional view of ITER

Full poloidal length TBM first wall (FW) Full poloidal length TBM first wall (FW) mock-upmock-up

Fabricated FW mockupFabricated FW mockup

Cross SectionCross Section

~18c~18cmm 8mm8mm

10 10 micronsmicrons

front platefront plate

rectangulrectangular tubear tube

rectangulrectangular tubear tube

1500mm1500mmLL x x 176mm176mmWW

250mm250mm

1500mm1500mm

WCSB TBM WCSB TBM (a sub-(a sub-

module)module)

FWFW（（ F82H)F82H)

Overall view of the TBM-FW mockup Overall view of the TBM-FW mockup with coolant manifoldswith coolant manifolds

front platefront plate

- HIP condition- HIP condition ：：11001100ººC, 150MPa, 2hC, 150MPa, 2h

- 15 rectangular coolant - 15 rectangular coolant channelschannels

High heat flux testHigh heat flux test

In ~0.5MW/mIn ~0.5MW/m22, 30sec, 80 cycles , 30sec, 80 cycles of heat load, hot spot due to of heat load, hot spot due to bond defect was not observed. bond defect was not observed. Expected heat removal Expected heat removal performance was performance was demonstrated. demonstrated.

HHF Test ConditionHHF Test ConditionHeat Flux: 0.5 MW/mHeat Flux: 0.5 MW/m22

Beam Pulse: 30 sBeam Pulse: 30 sCoolant Inlet P.Coolant Inlet P. ： ： 15 MPa15 MPaCoolant Inlet T.: 280 Coolant Inlet T.: 280 ooCCFlow velocity: 2 m/sFlow velocity: 2 m/s

HH++ Ion Beam Ion Beam

TBM FW TBM FW MockupMockup

Infrared camera ImageInfrared camera Image

Preliminary high heat flux test of the TBM-FW mockup has been carried Preliminary high heat flux test of the TBM-FW mockup has been carried out under high temperature pressurized coolant condition.out under high temperature pressurized coolant condition.Further thermal cycling test of this mockup is planned in this year.Further thermal cycling test of this mockup is planned in this year.

Development / provisional procurement activity of Development / provisional procurement activity of the ITER divertor outer vertical targetthe ITER divertor outer vertical target Small divertor mock-upsSmall divertor mock-ups Non-destructive examination by using infrared Non-destructive examination by using infrared

thermographythermography

Development of the first wall of the ITER test Development of the first wall of the ITER test blanket module (TBM) blanket module (TBM) Provisional high heat flux test of the full-poloidal length Provisional high heat flux test of the full-poloidal length

TBM first wall mock-upTBM first wall mock-up

Development of the DEMO divertorDevelopment of the DEMO divertor Small divertor mock-ups made of Small divertor mock-ups made of ferritic steel withferritic steel with

monoblock tungsten armormonoblock tungsten armor

ContentsContents

Small divertor mock-up for DEMO Small divertor mock-up for DEMO applicationapplication

As a basic R&D to achieve DEMO divertor, a small mock-up As a basic R&D to achieve DEMO divertor, a small mock-up made of F82H with monoblock tungsten armor has been made of F82H with monoblock tungsten armor has been fabricated by using HIP bonding technique.fabricated by using HIP bonding technique.

at 5 MW/m2

(EB heating)

The central two tungsten lamellae were overheated due to the The central two tungsten lamellae were overheated due to the delamination of the HIP bonded interface. Further improvements of delamination of the HIP bonded interface. Further improvements of the HIP bonding condition for the F82H and tungsten joint are the HIP bonding condition for the F82H and tungsten joint are essential. essential.

High heat flux High heat flux testtest

HIP@970oC x 150MPa x 2h750oC x 1.5h

SummarySummary R&D activities on the PFCs for ITER and DEMO reactor R&D activities on the PFCs for ITER and DEMO reactor

have extensively been performed in JAEA. have extensively been performed in JAEA. For the ITER divertor components, the braze bonding For the ITER divertor components, the braze bonding

technique has been optimized. The ITER divertor technique has been optimized. The ITER divertor qualification prototype has successfully been fabricated qualification prototype has successfully been fabricated and soon be high heat flux tested in Efremov institute. and soon be high heat flux tested in Efremov institute.

In addition, the thermal performance of the TBM first In addition, the thermal performance of the TBM first wall with full poloidal length have successfully been wall with full poloidal length have successfully been demonstrated, and also the soundness of the HIP joint demonstrated, and also the soundness of the HIP joint of F82H was demonstrated. of F82H was demonstrated.

On the other hand, the HIP bonding condition for the On the other hand, the HIP bonding condition for the tungsten and F82H joint should be investigated and tungsten and F82H joint should be investigated and improved as a bonding method for the DEMO divertor.improved as a bonding method for the DEMO divertor.

Further development of the bonding technique should Further development of the bonding technique should be necessary to realize the DEMO divertor. The be necessary to realize the DEMO divertor. The development of the structural material (F82H) will be development of the structural material (F82H) will be continued, in parallel to the development of the TBM continued, in parallel to the development of the TBM components.components.