DCLL Blanket for ARIES-AT:Major Changes to Radial Build

and Design Implications

DCLL Blanket for ARIES-AT:Major Changes to Radial Build

and Design Implications

L. El-GuebalyFusion Technology Institute

UW - Madison

ARIES-Pathways Project MeetingDecember 12 - 13, 2007

Georgia Tech

2

Objectives

• Redesign ARIES-AT with DCLL system (a la ARIES-CS).

• Define new IB, OB, Div radial builds for ARIES-AT-DCLL.

• Assess implications of DCLL blanket on ARIES-AT engineering,physics, and economics.

3

ARIES-AT Reference Design

Fusion Power 1755 MWMajor Radius 5.2 mMinor Radius 1.3 mPeak Γ @ IB, OB, Div 3.1, 4.8, 2 MW/m2

SiC/SiC Composite StructureLiPb/SiC BlanketDiscrete LiPb ManifoldsHT S/C Magnet @ 70-80 KNo W on FW

Calculated Overall TBR 1.1 ηth ~ 60%Availability 85%

Plasma Control:5 W Shells on IB and OB2 Vertical Position Coils2 Feedback Coils

4

ARIES-AT Radial Builds: IB, OB, Div(SiC Structure)

4 cm

Ver

tical

St

abili

zing

She

ll

SOL

Vac

uum

Ves

sel

HT

Shie

ldG

ap

Gap

+ T

h. In

sula

tion

Win

ding

Pac

k

Plas

ma

5 2 ≥215 171425

Coi

l Cas

e

1445

4 cm

Ver

tical

St

abili

zing

She

ll

Blan

ket-I

I

Coi

l Cas

e

FW/B

lank

et-I

30

1 cm

RW

MSh

ell

1

Gap

SOL

Vac

uum

Ves

sel

(not

rew

elda

ble )

Gap

Gap

+ T

h. In

sula

tion

Win

ding

Pac

k

Plas

ma

3512 241714 40

Coi

l Cas

e

5C

oil C

ase

FW/B

lank

et

4 cm

Ver

tical

St

abili

zing

She

ll

3

Gap

HT

Shie

ld 4 cm

Ver

tical

St

abili

zing

She

ll

5 cm

Inboard

Outboard Divertor

Vacuum Vessel(not reweldable)

Gap

Gap + Th. Insulation

Winding Pack

Coil Case

Coil Case

Divertor SystemGap

40

30

14

17

14

HT Shield(replaceable)

HT Shield

Gap

3.35cm

151

2

5

ARIES-AT Vacuum Vessel(FS Structure)

3-D Cutway View of Vacuum Vessel

Notes:Area for plumbing connections is shown as a step, but are local cuttoutsRibs are not shownStructure will be welded as required to form complete assembly

B

IB and Top/Bottom VV(not-reweldable)

Dimension and Composition

40 cm IB VV: 13% FS, 22% H2O, 65% WC Filler40 cm T/B VV: 13% FS, 22% H2O, 65% B-FS Filler25 cm OB VV: 30% FS, 70% H2O.

View B - Rib Detai l

2 cm (0.787"), Typ

2 cm (0.787"), Typ

2 cm (0.787"), Typ

(10 x view)

2 cm plate

2 cm plate

2 cm rib

6

ARIES-AT TF/PF Magnet(High-Temp S/C @ 70-80 K)

Composition:7% YBCO7% CeO2 insulator72% Inconel-6250.5% Ag13.5% GFF Polyimide insulator.

Conduction cooling of WP from coil case.

Coil case contains 5% LN cooling channels.

YBCOCeO2

Sliver

Inconel-625 Structure

WindingPack

7

ARIES-AT Blanket Options

Reference ARIES-ATOB Blanket

ARIES-AT-DCLL Blanket(a la ARIES-CS)

3.8

cm F

W

5 cm

Bac

k W

all

Breeding Zone-I

Breeding Zone-II

0.5 cmSiC Insert

1.5 cm FS/He

1.5

cm F

S/H

e

Breeder LiPbCoolant LiPbStructure SiC

Breeder LiPbCoolant He and LiPbStructure FS

SiC Structure FS Structure

8

ARIES-AT CompositionsARIES-AT-LiPb/SiC ARIES-AT-DCLL (Reference Design)

Inboard:FW/Blanket 81% LiPb, 19%SiC 79% LiPb, 8% He,

6% FS, 7%SiC inserts

HT Shield 15%SiC, 10% LiPb, 15%FS, 10% He,70% B-FS Filler , 5% W shells 75% B-FS Filler

Outboard:FW/Blanket-I 80% LiPb, 20%SiC 79% LiPb, 8% He,

6% FS, 7%SiC inserts

FW/Blanket-II 77% LiPb, 20%SiC, 79% LiPb, 8% He,3% W shells 6% FS, 7%SiC inserts

HT Shield 15%SiC, 10% LiPb, 15%FS, 10% He,75% B-FS Filler 75% B-FS Filler

Top/Bottom:Divertor System 40%SiC, 50% LiPb, 10% W 33% FS, 4% W, 63% He

Replaceable HT Shield 15%SiC, 10% LiPb, 15%FS, 10% He,75% FS Filler 75% B-FS Filler

Permanent HT Shield 15%SiC, 10% LiPb, 15%FS, 10% He,75% B-FS Filler 75% B-FS Filler

9

ARIES-AT Radiation Limits andKey Parameters

Calculated Overall TBR 1.1Net TBR ~1.01 (for T self-sufficiency)

Damage to Structure 3% Burnup - SiC/SiC composites (for structural integrity) 200 dpa - advanced FS

Helium Production @ VV 1 He appm (for reweldability of FS)

HT S/C TF & PF Magnets (@ 70-80 K): Peak Fast n fluence to YBCO (En > 0.1 MeV) 1019 n/cm2

Peak Nuclear heating highPeak Dose to GFF Polyimide insulator < 1011 rads

Plant Lifetime 40 FPY

Availability 85%

Operational Dose to Workers and Public < 2.5 mrem/h

10

Changes and UpdatesARIES-AT-LiPb/SiC ARIES-AT-DCLL*

(Reference Design)

Peak NWL @ IB, OB, Div 3.1, 4.8, 2 MW/m2 3.1, 4.8, 2 MW/m2

(to be updated)

FS structure ORNL FS MF82H FS

LiPb:Li enrichment 90% 90%Average temp 700 oC 580 oCDensity 8.8 g/cc 9 g/cc

OB blanket Two segments One segment

W shells:Two 4-cm-thick VS shells on IB: Between IB blanket & shield Between IB blanket & shield? (toroidally continuous)Two 4-cm-thick VS shells on OB: Between OB blanket segments Behind OB blanket? (toroidally continuous)1-cm-thick RWM shell on OB: Between OB blanket segments Behind OB blanket?

Shield coolant LiPb He

IB Blanket-shield gap 1 cm ---

VV model Homogeneous Heterogeneous with 2-cm-thick plates

Cross section data library IAEA FENDL-2 IAEA FENDL-2.1

11

IB Radial Build(3.1 MW/m2 Peak NWL)

SOL

Vac

uum

Ves

sel

Gap

Gap

+ T

h. In

sula

tion

Win

ding

Pac

k

Plas

ma

362 241714 40

Coi

l Cas

e

5

Coi

l Cas

e

FW/B

lank

et( L

iPb/

He/

FS)

3

HT

FS S

hiel

d

5

141 cm

SOL

Vac

uum

Ves

sel

(not

rew

elda

ble )

Gap

Gap

+ T

h. In

sula

tion

Win

ding

Pac

k

Plas

ma

3512 241714 40

Coi

l Cas

e

5C

oil C

ase

FW/B

lank

et( L

iPb/

SiC

)

4 cm

Ver

tical

St

abili

zing

She

ll

3

Gap

HT

SiC

Shi

eld

4 cm

Ver

tical

St

abili

zing

She

ll

5

ARIES-ATReference IB-RB

ARIES-AT-DCLLIB-RB-I

B/S contain ~8 cm He

12

IB Breeding & Radiation Damage(Replacing IB Shield by Blanket)

3624

FW/B

lank

et( L

iPb/

He/

FS)

HT

FS S

hiel

d

60 cm

0

1

2

3

4

5

30 40 50 60Fas

t N

eutr

on

Flu

ence

at

Mag

net

(1019

n/c

m2 @

40

FP

Y)

IB Blanket Thickness (cm)

More shield needed to protect magnet

Limit

45 cm blanket alongwith 20 cm shield

(65 cm total)protects magnet

0

20

40

60

80

100

30 40 50 60

He

Pro

du

ctio

n a

t IB

VV

(ap

pm

@ 4

0 F

PY

)

IB Blanket Thickness (cm)

IB VV is not reweldable

Limit

100

200

300

400

500

600

700

800

30 40 50 60

Pea

k d

pa

at IB

Sh

ield

(dp

a @

40

FP

Y)

IB Blanket Thickness (cm)

45 cm IB Blanket does not protect shield for 40 FPY

Limit

0.2

0.3

0.4

30 35 40 45 50 55 60

IB C

on

trib

uti

on

to

Ove

rall

TB

R

IB Blanket Thickness (cm)

90% 6Li Enrichment

13

Recommended ARIES-AT-DCLLIB Radial Build

(no LiPb/He Manifolds; no W Shells)

SOL

Vac

uum

Ves

sel

Gap

Gap

+ T

h. In

sula

tion

Win

ding

Pac

k

Plas

ma

362 241714 40

Coi

l Cas

e

5C

oil C

ase

FW/B

lank

et( L

iPb/

He/

FS)

3

HT

FS S

hiel

d

5 141 cm

ARIES-AT-DCLLIB-RB-I

Vac

uum

Ves

sel

(not

rew

elda

ble )

Gap

Gap

+ T

h. In

sula

tion

Win

ding

Pac

k

452 201714 40

Coi

l Cas

e

5

Coi

l Cas

e

FW/B

lank

et( L

iPb/

He/

FS)

3

HT

FS S

hiel

d(r

epla

ceab

le)

SOL

Plas

ma

5 146 cm

ARIES-AT-DCLLRecommended IB RB

No LiPb/He ManifoldsNo W Shells

14

OB Radial Build(4.8 MW/m2 Peak NWL)

≥ 166 cm

ARIES-ATReference OB-RB

ARIES-AT-DCLL

4 cm

Ver

tical

St

abili

zing

She

ll

SOL

Vac

uum

Ves

sel

HT

SiC

Shi

eld

Gap

Gap

+ T

h. In

sula

tion

Win

ding

Pac

k

Plas

ma

5 2 ≥315 171425

Coi

l Cas

e

1445

4 cm

Ver

tical

St

abili

zing

She

ll

Blan

ket-I

I(L

iPb/

SiC

)

Coi

l Cas

e

FW/B

lank

et-I

( LiP

b/Si

C)

30

1 cm

RW

MSh

ell

1

Gap

SOL

Vac

uum

Ves

sel

HT

FS S

hiel

dG

ap

Gap

+ T

h. In

sula

tion

Win

ding

Pac

k

Plas

ma

5 2 ≥215 171425

Coi

l Cas

e

1476

Coi

l Cas

e

FW/B

lank

et(L

iPb /

He/

FS)

OB-RB-I

B/S contain ~10 cm He

15

Calculated TBR Should be ≥ 1.1

• 45 cm IB blanket and 80 cm OB blanket meet breeding requirement.

• Will iterate with UCSD to adjust FW/blanket composition, then readjust overall

TBR and IB/OB radial builds.

0.2

0.3

0.4

0.5

0.6

0.7

0.8

0.9

30 40 50 60 70 80 90

TB

R

Blanket Thickness (cm)

IB

OB

90% 6Li Enrichment

16

OB Breeding & Radiation Damage (Replacing OB Shield by Blanket)

HT

FS S

hiel

d

1576

FW/B

lank

et(L

iPb/

He/

FS)

91 cm

50

100

150

200

250

70 75 80 85 90

Pea

k d

pa

at O

B S

hie

ld(d

pa

@ 4

0 F

PY

)

OB Blanket Thickness (cm)

OB Shield is overprotected

Limit

0

2

4

6

8

10

70 75 80 85 90

He

Pro

du

ctio

n a

t O

B V

V(a

pp

m @

40

FP

Y)

OB Blanket Thickness (cm)

More OB shield needed for reweldability of VV

Limit

80 cm blanket alongwith 20 cm shield

(100 cm total)protects VV and

magnet0

1

2

3

4

5

70 75 80 85 90Fas

t N

eutr

on

Flu

ence

at

Mag

net

(1019

n/c

m2 @

40

FP

Y)

OB Blanket Thickness (cm)

More shield needed to protect magnet

Limit

0.7

0.8

0.9

70 75 80 85 90OB

Co

ntr

ibu

tio

n t

o O

vera

ll T

BR

OB Blanket Thickness (cm)

90% 6Li Enrichment

17

ARIES-AT-DCLL

≥ 175 cm

SOL

HT

FS S

hiel

d

Plas

ma

5 2080

FW/B

lank

et(L

iPb /

He/

FS)

Vac

uum

Ves

sel

Gap

Gap

+ T

h. In

sula

tion

Win

ding

Pac

k

2 ≥2 171425

Coi

l Cas

e

14

Coi

l Cas

e

ARIES-AT-DCLL

≥ 166 cm

SOL

Vac

uum

Ves

sel

HT

FS S

hiel

dG

ap

Gap

+ T

h. In

sula

tion

Win

ding

Pac

k

Plas

ma

5 2 ≥215 171425

Coi

l Cas

e

1476

Coi

l Cas

e

FW/B

lank

et(L

iPb /

He/

FS)

OB-RB-I

Recommended ARIES-AT-DCLLOB Radial Build

(no LiPb/He Manifolds; no W Shells)

Recommended OB RB

No LiPb/He ManifoldsNo W Shells

18

Divertor Radial Build (2 MW/m2 Peak NWL)

ARIES-ATReference D-RB ARIES-AT-DCLL

Vacuum Vessel(not reweldable)

Gap

Gap + Th. Insulation

Winding Pack

Coil Case

Coil Case

Divertor SystemGap

40

30

14

17

14

HT SiC Shield(replaceable)

HT SiC Shield

Gap

3.35cm

151

2

133.

35 c

m w

/o g

aps

D-RB-I

Vacuum Vessel

Gap

Gap + Th. Insulation

Winding Pack

Coil Case

Coil Case

Divertor System

40

30

14

17

14

HT FS Shield

Gap

20

2

3

D/S

con

tain

~16

cm

He

19

Divertor Radiation Damage (Adding Replaceable Shield)

• 18 cm replaceable shield and 40 cmpermanent shield protect VV.

• Shield and 27 cm VV protect magnet.

200

400

600

800

1000

0 5 10 15 20Pea

k d

pa

at P

erm

anen

t S

hie

ld(d

pa

@ 4

0 F

PY

)

Replaceable Shield Thickness (cm)

18 cm Replaceable shield protects permanent shield

Limit

0

10

20

30

40

50

60

0 5 10 15 20

He

Pro

du

ctio

n a

t V

V(a

pp

m @

40

FP

Y)

Replaceable Shield Thickness (cm)

40 cm Thick permanent shield needed for reweldability of VV

Limit

30 cm Permanent Shield

0

1

2

3

4

0 5 10 15 20Fas

t N

eutr

on

Flu

ence

at

Mag

net

(1019

n/c

m2 @

40

FP

Y)

Replaceable Shield Thickness (cm)

Magnet is over protected

Limit

30 cm Permanent Shield40 cm VV

20

ARIES-AT-DCLLNo LiPb/He Manifolds

D-RB-IARIES-AT-DCLL

133.

35 c

m w

/o g

aps

Vacuum Vessel(not reweldable)

Gap

Gap + Th. Insulation

Winding Pack

Coil Case

Coil Case

Divertor System

40

30

14

17

14

HT FS Shield

Gap

20

2

3

Recommended ARIES-AT-DCLLDivertor Radial Build

(no LiPb/He Manifolds)

150

cm w

/o g

aps

Vacuum Vessel(reweldable)

Gap

Gap + Th. Insulation

Winding Pack

Coil Case

Coil Case

Divertor System

27

40

14

17

14

HT FS Shield

Gap

20

2

3HT FS Shield(replaceable) 18

Recommended Div RB

21

Radiation LevelIB OB Div. Limit

Peak NWL (MW/m2) 3.1 4.8 2

dpa at shield (dpa @ 40 FPY): 200Replaceable 540 --- 1030Permanent ---# 108 190

He production at manifolds(He appm @ 40 FPY) --- --- --- 1

He production at VV(He appm @ 40 FPY) 19** 0.9 0.95 1

Magnet @ 70-80 K:Fast neutron fluence 0.9 0.8 0.9 1 (1019 n/cm2 @ 40 FPY)

Nuclear heating (mW/cm3) 0.2 4* 0.3 high___________# May divide IB shield into replaceable and permanent components, ~10 cm each. Attach replaceable shield to Back Wall of blanket.** Reweld at top/bottom, not around midplane.* Will add boride in VV to lower magnet heating and activation.

22

Impact of DCLL System onARIES-AT Economics

ARIES-AT-LiPb/SiC ARIES-AT-DCLL Cost of (Reference Design) ARIES-AT-DCLL

Major radius 5.2 m > 5.2 m ↑

Calculated overall TBR 1.1 1.1FW/blanket lifetime 4 FPY 2.8 FPY ↑

Overall energy multiplication 1.1 ~1.15 ↓

Structure unit cost (2004 $) 510 $/kg 103 $/kg ↓

ηth ~ 60% 40-45% ↑

Cost of heat transfer/transport system $126M > $300M ↑ (1992 $)He pumping power --- > 100 MWe ↑

Level of Safety Assurance (LSA) factor 1 2 ↑

COE: in 1992 $ 48 mills/kWh ~ 60 mills/kWh ↑

in 2004 $ 60 mills/kWh ~ 80 mills/kWh

23

Observations and QuestionsObservations:

– DCLL radial builds increased by 5-17 cm, mainly due to He cooling ⇒ Larger machine– DCLL Blanket segmentation not allowed ⇒ Large volume of radwaste OB shells will be located outside blanket, far away from

plasma ⇒ No impact on breeding Impact on physics and cost?

– Breeding with < 90% enrichment (for larger breeding margin) requires fairly thick IB and OB blankets– IB replaceable shield could be divided into replaceable and permanent components to minimize radwaste

stream– Boride material will be added to OB VV to reduce magnet heating and activation– LiPb and He manifolds will increase radial standoff and should not be placed at IB– Penetration shield should surround pumping ducts to limit radiation damage at VV and magnet– NWL distribution will be updated using actual neutron source profile within plasma, per Wilson (UW)– Future radial build will include manifolds and W shells.

Questions :– Discrete or continuous LiPb/He manifolds?– Size, composition, and location of manifolds?– Continue using HT YBCO TF/PF magnets? Switch to LT Nb3Sn magnet?– Impact of new shell location (outside sizable IB and OB blankets) on beta and other physics parameters?