Suzuki Konishi

7/28/2019 Suzuki Konishi

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Japan considerations on designand qualification of PFC's

for near term machines (ITER)

Satoshi Suzuki1, Satoshi Konishi2

1 Japan Atomic Energy Agency

2 Kyoto University


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Contents

Development / provisional procurement activity of theITER divertor outer vertical target

Small divertor mock-ups

Non-destructive examination by using infrared thermography

Development of the first wall of the ITER test blanketmodule (TBM)

Provisional high heat flux test of the full-poloidal length TBM firstwall mock-up

Development of the DEMO divertor

Small divertor mock-ups made of ferritic steel with tungstenarmor


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Contents


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ITER Plasma Facing Components

Among the divertor high heat fluxcomponents, JAEA is going toprocure all of the outer verticaltarget

22 plasma facing units / 1 cassette

54 cassettes + 6 spares

--> 1320 plasma facing units

Outer vertical target (JA)

Inner vertical target (EU)

Dome(RF)

Cassettebody (EU)Plasma

Troidalcoil

Divertor

First wall/Blanket

6.2m

Test BlanketModule(TBM)

Cross sectional view of ITER

ITER divertor


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Outer vertical target Design heat flux

Tungsten part : 5MW/m2

CFC (Carbon Fiber Composite) part :10 - 20MW/m2

Coolant condition

Water, 4MPa, 100oC

Swirl flow by twisted tape (CFC part)

Bonding of armor materials

Braze

HIP (Hot Isostatic Pressing)

Prior to the procurement of the verticaltarget components, the manufacturingprocess and the thermal performance ofthe components should bevalidated/demonstrated by using small

mock-ups. ("Prequalification" activity)

Tungsten

CFC

Tungsten

CFC

28mm

Soft copper

Copper alloy

Outer vertical target (1 cassette)

with "Monoblock" geometry


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Optimization of the manufacturing processby using small mock-ups

Armor : CFC (CX-2002U) Tube : CuCrZr

Bonding : Brazing (Tbraze=980oC)

Ni-Cu-Mn

Ti-Cu-Ni

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

Accuracy of machining of CFC hole

+/- 5 microns to the target value

High heat flux test has beenperformed to check the soundness ofthe braze interface and todemonstrate the thermalperformance.

A small vertical target mock-upsimulating the CFC part of thevertical target

CFC

28mm

28mm

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


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High heat flux test of the small mock-upsand fabrication of a qualification prototype

Braze filler : Ni-Cu-Mn (980oC x0.5h, followed by Ar gas

quench) Metalizing : Present (Ti-Cu, 7.5

- 10%-Ti) Aging : 475oC x 2h Finally, the mock-up fabricated

by using parameters above

could withstand the heat flux of20MW/m2 for 1000 cycles.

at 5 MW/m2

(EB heating)

ITER vertical target

Qualification Prototype

Based on the successful result of the smallmock-ups, a medium scale mock-up(Qualification Prototype) has beenmanufactured.

This mock-up includes most of the criticaltechnical issues (bonding of CFC/Cu,curved cooling tube, etc...) on thefabrication of the ITER divertor vertical

target. This mock-up will be high heat fluxtested in Efremov institute in 2008.


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High heat flux test of the small mock-upsand fabrication of a qualification prototype

Braze filler : Ni-Cu-Mn (980oC x0.5h, followed by Ar gas

quench) Metalizing : Present (Ti-Cu, 7.5

- 10%-Ti) Aging : 475oC x 2h Finally, the mock-up fabricated

by using parameters above

could withstand the heat fluxof 20MW/m2 for 1000 cycles.

at 5 MW/m2

(EB heating)

ITER vertical target

Qualification Prototype

The high heat flux test of the first mock-up(VTQP-1) has been completed in November,2008. This mock-up has successfullywithstood the heat flux requirements asfollows; CFC : 10MW/m2 x 1000 + 20MW/m2 x

1000cycles W : 3MW/m2 x 1000 + 5MW/m2 x 1000 cycles

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

l f f l


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Development of a new NDE facility"FIND" (Facility of Infrared Non-destructive

examination for Divertor) In parallel to the optimization of the manufacturing process,

acceptance test methods have also been provided.

In addition to the conventional methods (UT, RT, He leak testing forthe braze/weld joint), infrared thermography examination isessential for the non-destructive examination of the vertical target.

UT can detect theinterfacial defectsbetween CuCrZr tubeand soft copper

interlayer.

CFC (porous)

UT sensor

Internal defect of CFCor interfacial defectbetween CFC and softcopper can not be

detected by UT.

CFC (porous)

l f f ili


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examination for Divertor)

D l f NDE f ili


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examination for Divertor)

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

Time-to-time differential of the thermal transient between defected and

non-defected mock-ups gives quantitative evaluation of the defect size andthe location with the help of FEM analysis.


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Contents


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ITER TBM Test Program

ITER TBM Program is to test thenecessary functions of DEMO Blanketin the real fusion environment withtest module scalable to DEMO blanket.

Demonstration of production offusion fuel tritium

Demonstration of extraction ofenergy

Demonstration of shieldingperformance

ITER TBM Test Program is one of the

most important development step. Based on the results from the basic

R&Ds on material testing andfabrication trial, near-full-scale mock-up has successfully been developed.

Plasma

Troidalcoil

Divertor

First wall/Blanket

6.2m

Test BlanketModule(TBM)

Cross sectional view of ITER


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

Fabricated FW mocku Cross Section

~18cm8mm

10 microns

front plate

rectangulartube

rectangulartube

1500mmL x 176mmW250mm

1500mm

WCSB TBM(a sub-module)

FW

F82H)

Overall view of the TBM-FW mockup

with coolant manifolds

front plate

- HIP condition1100C, 150MPa, 2h

- 15 rectangular coolant channels


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High heat flux test

In ~0.5MW/m2, 30sec, 80 cycles of

heat load, hot spot due to bonddefect was not observed.Expected heat removal performancewas demonstrated.

HHF Test Condition

Heat Flux: 0.5 MW/m2

Beam Pulse: 30 sCoolant Inlet P. 15 MPaCoolant Inlet T.: 280 oCFlow velocity: 2 m/s

H+

Ion Beam

TBM FWMockup

Infrared camera Image

Preliminary high heat flux test of the TBM-FW mockup has been carried out

under high temperature pressurized coolant condition.Further thermal cycling test of this mockup is planned in this year.


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Small divertor mock-ups made offerritic steel withmonoblocktungsten armor

Contents


17/18

Small divertor mock-up for DEMO application As a basic R&D to achieve DEMO divertor, a small mock-up made of

F82H with monoblock tungsten armor has been fabricated by usingHIP bonding technique.

at 5 MW/m2

(EB heating)

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

High heat flux test

HIP@970oC x150MPa x 2h

750o

C x 1.5h


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

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

has been optimized. The ITER divertor qualification prototypehas successfully been fabricated and soon be high heat fluxtested in Efremov institute.

In addition, the thermal performance of the TBM first wall withfull poloidal length have successfully been demonstrated, andalso the soundness of the HIP joint of F82H was demonstrated.

On the other hand, the HIP bonding condition for the tungstenand F82H joint should be investigated and improved as a

bonding method for the DEMO divertor. Further development of the bonding technique should be

necessary to realize the DEMO divertor. The development ofthe structural material (F82H) will be continued, in parallel tothe development of the TBM components.

Documents

Suzuki Konishi