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Progress on the Progress on the

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Configuration Design of the Fusion Power Core for the ACT Draft XR Wang MS Tillack S Malang Sept 29 2011 One sector 225 degree ARIESACT 1BAggressive Physics Posted at ARIES Web June 8 2011 ID: 577912

cooled sic blanket shield sic cooled shield blanket structure divertor design helium pipes access option act tube flow power

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Slide1

Progress on the Configuration Design of the Fusion Power Core for the ACT(Draft)

X.R. Wang

M.S. Tillack

S. Malang

Sept. 29, 2011Slide2

One sector (22.5 degree)ARIES-ACT 1B(Aggressive Physics), Posted at ARIES Web: June 8, 2011R=5.5 mA=1.375 mElongation=2.2Results of CAD analysis: Total plasma surface area=~475 m

2

Total plasma volume=~417 m

3

Total FW surface area=~452 m2(AIB=140 m2,AOB=312 m2)Total Divertor surface area=~143 m2

OB FW

Thickness of IB/OB SOL at mid-plane=10 cm

Curved FWOB divertor location=R-a/2IB divertor location=R-a

Plasma

OB divertor plate

IB divertor plate

Dom plate

IB FW

OB FW

Geometry Definitions (from Chuck):Slide3

Design Options of the ACT-1b Fusion Power Core

Design Option #1

Design Option #2

IB Blanket

Pb83Li17 cooled SiC/SiC structurePb83Li

17 cooled SiC/SiC structureIB Shield

Pb83Li

17 cooled steel and SiC/SiC tubeHelium-cooled steel structure and ODS tube?1st OB Blanket

Pb

83Li17 cooled SiC/SiC structure

Pb

83Li17 cooled SiC/SiC structure

2nd OB Blanket

Pb83Li

17 cooled SiC/SiC structure

Pb83Li17 cooled SiC/SiC structure

OB Shield

Pb83Li17 cooled steel and SiC/SiC tubeHelium-cooled steel structure and ODS tube?

Upper/Lower Divertors Helium-cooled W-based divertor

Helium-cooled W-based divertorSlide4

Power core configuration of the ACT 1B (Design option #1: Pb-Li cooled shield) Thickness radius (ACT-1b straw-man)

Inboard:

TF coil annulus: 0.33 m

Vacuum vessel: 0.4 m

HT shield: 0.23 mIB blanket: 0.34 mOutboard:1

st Blanket: 0.29 m

2nd Blanket: 0.43 m

HT shield: 0.29 mVacuum vessel: 0.25 mTF coil annulus: 0.33 mVertical build:

HT shield: 0.3 mReplaceable HT shield: 0.29 m

Vacuum vessel: 0.4 m

All LM access pipes are designed as concentric tubes with the cold inlet flow (~650 °C) in the annulus, cooling in this way the inner tube (1100 °C) to the allowable temperature (~1000 °C) of the SiC/SiC.

He access pipes are also designed as concentric tubes (700/800 °C for outer/inner tubes)Slide5

Circuit 1: series flow through the inboard shield and inboard blanket regionCircuit 2: flow though the first outboard blanket region

Circuit 3:

series flow through the outboard shield and the second outboard

blanket region

Circuit 4: Helium-cooled the upper divertorCircuit 5:

Helium-cooled the lower divertor

Design Option of the Coolant RoutingSlide6

Design Option of the Access PipesSlide7

Bottom view showing the space of all access pipes (5 circuits)He access pipes

Pb-Li access

pipes

It is possible to make the Pb-Li access pipes bigger to reduce flow velocity

.Slide8

Power Core Configuration of the ACT 1B (Design Option #2: Helium-cooled Shield) In progress!