New Radial Build DataNew Radial Build Data

L. El-GuebalyFusion Technology Institute

UW - Madison

With input from:R. Raffray, S. Malang, X. Wang (UCSD),

L. Bromberg (MIT)

ARIES-CS Project MeetingNovember 17 – 18, 2005

UCSD

2

Recent Changes to Radial Build(3 FP Configuration; LiPb/FS System)

6 Shield-only zones:• 20 cm thick He manifolds* added; two modules per zone; one He access

tube per module (32 cm ID).• Issues and concerns:

• Impact of manifolds on overall machine size and cost• Impact of tubes on reweldability of manifolds• Tubes remove ~40 cm of shielding materials fi hot spots at magnet• Thick local shield needed behind VV to protect magnet.

• Rewelding of VV in this area can be avoided, per Siegfried.

Nominal Blanket/shield zone:• HT shield increased from 18 cm to 28 cm to protect manifolds.• Tubes remove ~30 cm of shielding materials fi hot spots at magnet• 206 local shields needed to protect VV and magnet.• Observations:

• No major impact on machine size• More expensive shield.

____________* Siegfried suggests 15 cm thick manifolds.

3

Recent Changes to Radial Build (Cont.)(LiPb/FS System)

New magnet design:• 4K magnet composition, per Leslie:

18.5% Incoloy-90848.2% Cu12.8% Nb3Sn10.0% Insulation*10.5% Liquid He

• Winding pack dimension not available. 30 x 30 cm assumed.• Thickness of external and side structures not available. 10-20 cm assumed.

• Monitor:• Peak (< 2 mW/cm3) and• Total nuclear heating at magnet and cryogenic heat load• dpa to Cu stabilizer (< 6x10-3)

____________* Type not available. Used GFF polyimide as placeholder.

New magnet has no major impact on radial build definition

4

9/05 Radial Build(3 MW/m2 peak G)

Thickness(cm)

D ≥ 171 cm| |

SOL

Vac

uum

Ves

sel

Back

Wal

l

Gap

Thickness(cm)

Gap

+ T

h. In

sula

tor

Coi

l Cas

e & In

sula

tor

Win

ding

Pac

k

Plas

ma

5 2 217 312.228

| |Dmin = 119 cm

ShieldOnlyZone

@ Dmin

5

Blanket/ShieldZone

FW

3.8

Exte

rnal

Str

uctu

re

18

1.5 cm FS/He

FW/Blkt/BW

WC

Shi

eld-

I(r

epla

ceab

le)

38

WC

Shi

eld-

II(p

erm

anen

t)

SOL

Vac

uum

Ves

sel

HT

FS S

hiel

d

Gap

3.8

cm F

W

Gap

+ T

h. In

sula

tor

Win

ding

Pac

k

Plas

ma

5 2 ≥ 218 312.228

Coi

l Cas

e & In

sula

tor

5 cm

Bac

k W

all

Exte

rnal

Str

uctu

re

18

25 cmBreeding

Zone-I

25 cmBreeding Zone-II

0.5 cmSiC Insert

1.5 cm FS/He

1.5

cm F

S/H

e

63| | 35

Man

ifold

s

VV

BlanketShield

Magnet

WC

Shi

eld-

only

or

Tran

sitio

n R

egio

n

Manifolds

5

New Radial Build(3 MW/m2 peak G, changes marked in red)

Thickness(cm)

| |Thickness

(cm)

ShieldOnlyZone

@ Dmin

Blanket/ShieldZone

VV

BlanketShield

Magnet

WC

Shi

eld-

only

or

Tran

sitio

n R

egio

n

Manifolds

FW/Blkt/BW

D ≥ 181 cm

SOL

Vac

uum

Ves

sel

HT

FS S

hiel

d

Gap

3.8

cm F

W

Gap

+ T

h. In

sula

tor

Win

ding

Pac

k

Plas

ma

5 2 ≥228 302.228

Coi

l Cas

e & In

sula

tor

5 cm

Bac

k W

all

Exte

rnal

Str

uctu

re

10

25 cmBreeding

Zone-I

25 cmBreeding Zone-II

0.5 cmSiC Insert

1.5 cm FS/He

1.5

cm F

S/H

e

63| | 35

He &

LiP

b M

anifo

lds

Vac

uum

Ves

sel

Gap

Gap

+ T

h. In

sula

tor

Coi

l Cas

e & In

sula

tor

Win

ding

Pac

k

Plas

ma

2 2 302.228

| |Dmin = 139 cm

Exte

rnal

Str

uctu

re

10

SOL

Back

Wal

l

5 17 5

FW

3.8

1.5 cm FS/He

WC

Shi

eld-

I(r

epla

ceab

le)

38W

C S

hiel

d-II

(per

man

ent)

He M

anifo

lds

20

6

Xn through He Access Tubes(3 MW/m2 peak G)

||Thickness

(cm)

ShieldOnlyZone

@ Dmin VV

BlanketShield

Magnet

WC

Shi

eld-

only

or

Tran

sitio

n R

egio

n

Manifolds

Thickness(cm)

Blanket/ShieldZone

| |

Vac

uum

Ves

sel

Gap

Loca

l Shi

eld

Coi

l Cas

e & In

sula

tor

Win

ding

Pac

k

Plas

ma

2 ? 302.228

Dmin > 139 cm

Exte

rnal

Str

uctu

re

10

SOL

B

W

5 17 5

FW

3.8

1.5 cm FS/He

WC

Shi

eld-

I (

repl

acea

ble)

38

W

C S

hiel

d-II

(p

erm

anen

t)

He M

anifo

lds

20D > 181 cm

SOL

Vac

uum

Ves

sel

FS S

hiel

d

3.8

cm F

W

Gap

+ T

h. In

sula

tor

Win

ding

Pac

k

Plas

ma

5 ? ≥228 302.228

Coi

l Cas

e & In

sula

tor

5 cm

BW

Exte

rnal

Str

uctu

re

10

25 cmBreeding

Zone-I

25 cmBreeding Zone-II

0.5 cmSiC Insert

1.5 cm FS/He

1.5

cm F

S/H

e

63| | 35

Man

ifold

s

Loca

l Shi

eld

He Tube(32 cm ID)

He Tube(32 cm ID)

7

Suggestion• To alleviate impact of access tubes on radial build, use LiPb,

instead of He, to cool shield-only zones that cover 5% of FWarea.

• Disadvantages:• WC shield operates at lower temperature fi slightly lower hth

• Advantages:• Lower impact on radial build and overall machine• Less severe streaming problem• Thinner local shield• Lower temperature during LOCA/LOFA

• Question: Could all HT shields be cooled with LiPb? Benefits: more compact nominal radial build, smaller He access

tube, less streaming, and thinner local shields.

8

Nominal, Transition, andShield-only Zones

| | WC-Shield only Zone (5%)

Transition Region (10%)

Nominal Blanket/shieldZone (85%)

Plasma

MagnetVacuum Vessel

WC-Shield-II

WC-Shield-I

Blanket

FS-Shield

FW SOL

Back Wall

Gap

Non-uniformBlanket

LiPb & He Manifolds

417

5

28

35

28

5438 ?

8

13

38

28

Dm

in =

119

cm ?

5 cm

Manifoldsto be added

¨

9

2 Shield-Only Zones Per Field period(3 FP Configuration, R= 8.25 m)

Shield-only zone (green), transition region (blue), and nominalblanket zone cover 5%, 10% and 85% of FW area, respectively

Toroidal Length of Field Period (~18 m)

Polo

idal

Len

gth

of F

ield

Per

iod

(~12

m)

Recommended locationsfor FW He in/out tubes

10

Magnet Cryogenic Heat Load

• Assumptions:• 2 MW/m2 average G• Continuous 4K structure surrounding winding packs• 300 We needed to remove 1 W of nuclear heating

• Roughly estimated 0.014 MW of nuclear heating.

Cryogenic load to remove nuclear heating ~ 4 MWe

Other non-nuclear heat load to magnet?

11

Future Plan

• Check effect of shield LiPb coolant on radial build.

• Post new radial build on UW website:http://fti.neep.wisc.edu/aries-cs/builds/build.html

• Optimize dimensions of local shield behind access tubes andconfirm VV/magnet protection with 3-D analysis.

12

ARIES-CS Publications

Submitted final manuscript to ICFRM-12 conference (Dec 4-9, 205, Santa Barbara):The Feasibility of Recycling and Clearance of Active Materials from FusionPower PlantsM. Zucchetti, L. El-Guebaly, R. Forrest, T. Marshall, N. Taylor, K. Tobita

Published full report as UW FDM:Current Challenges Facing Recycling and Clearance of Fusion Radioactive MaterialsL. El-Guebaly, R. Forrest, T. Marshall, N. Taylor, K. Tobita, M. Zucchetti,Available at: http://fti.neep.wisc.edu/pdf/fdm1285.pdf