New Radial Build Data. New Radial Build Data. L. El-Guebaly. With input from: R. Raffray, S. Malang, X. Wang (UCSD), L.

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1 New Radial Build Data New Radial Build Data L. El-Guebaly Fusion Technology Institute UW - Madison With input from: R. Raffray, S. Malang, X. Wang (UCSD), L. Bromberg (MIT) ARIES-CS Project Meeting November 17 18, 200 UCSD

2 Recent Changes to Radial Build (3 FP Configuration; LiPb/FS System) 6 -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 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 1 cm thick manifolds. 2

3 Recent Changes to Radial Build (Cont.) (LiPb/FS System) New magnet design: 4K magnet composition, per Leslie: 18.% Incoloy % Cu 12.8% Nb 3 Sn 10.0% Insulation* 10.% Liquid He Winding pack dimension not available. 30 x 30 cm assumed. Thickness of external and side structures not available cm assumed. Monitor: Peak (< 2 mw/cm 3 ) and Total nuclear heating at magnet and cryogenic heat load dpa to Cu stabilizer (< 6x10-3 ) New magnet has no major impact on radial build definition * Type not available. Used GFF polyimide as placeholder. 3

4 WC -only or Transition Region Magnet Manifolds Blanket VV Dmin = 119 cm External Structure D 171 cm Winding Pack External Structure Winding Pack Coil Case & Insulator Gap + Th. Insulator 2 Gap 0. cm SiC Insert Coil Case & Insulator 2 Gap + Th. Insulator 38 Gap 3 Manifolds 18 HT FS 2 cm Breeding Zone-II cm Back Wall FW/Blkt/BW 63 WC -II (permanent) 17 Back Wall 3.8 WC -I (replaceable) FW 2 cm Breeding Zone-I 3.8 cm FW 9/0 Radial Build (3 MW/m2 peak G) Thickness (cm) Blanket/ Zone Thickness (cm) Only Dmin

5 Magnet Manifolds 3.8 Blanket External Structure 20 2 Gap + Th. Insulator Coil Case & Insulator 38 2 He & LiPb Manifolds Dmin = 139 cm 10 D 181 cm External Structure Winding Pack Gap + Th. Insulator Coil Case & Insulator Gap 3 Winding Pack HT FS 0. cm SiC Insert Gap He Manifolds 2 cm Breeding Zone-II cm Back Wall FW/Blkt/BW 63 WC -II (permanent) 17 Back Wall 2 cm Breeding Zone-I FW 3.8 cm FW WC -I (replaceable) WC -only or Transition Region New Radial Build (3 MW/m2 peak G, changes marked in red) VV Thickness (cm) Blanket/ Zone Thickness (cm) Only Dmin

6 Magnet Manifolds 3.8 Blanket (32 cm ID) He Tube Dmin > 139 cm? VV External Structure D > 181 cm Winding Pack (32 cm ID) Gap + Th. Insulator Coil Case & Insulator External Structure Winding Pack? Coil Case & Insulator He Tube Local 3 Local Gap 0. cm SiC Insert Manifolds He Manifolds FS cm BW 63 WC -II (permanent) 2 cm Breeding Zone-II BW 2 cm Breeding Zone-I FW 3.8 cm FW WC -I (replaceable) WC -only or Transition Region Xn through He Access Tubes (3 MW/m2 peak G) 10 Thickness (cm) Blanket/ Zone Thickness (cm) Only Dmin

7 Suggestion To alleviate impact of access tubes on radial build, use LiPb, instead of He, to cool shield-only zones that cover % of FW area. Disadvantages: WC shield operates at lower temperature fi slightly lower h th 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. 7

8 Nominal, Transition, and -only Zones 3 Gap LiPb & He Manifolds Magnet 4 4 FS- Back Wall Blanket FW Non-uniform Blanket WC--II WC--I Manifolds to be added 38? 17 cm D min = 119 cm? Nominal Blanket/shield Zone (8%) Transition Region (10%) WC- only Zone (%) 8

9 2 -Only Zones Per Field period (3 FP Configuration, R= 8.2 m) Poloidal Length of Field Period (~12 m) Recommended locations for FW He in/out tubes Toroidal Length of Field Period (~18 m) -only zone (green), transition region (blue), and nominal blanket zone cover %, 10% and 8% of FW area, respectively 9

10 Magnet Cryogenic Heat Load Assumptions: 2 MW/m 2 average G Continuous 4K structure surrounding winding packs 300 W e needed to remove 1 W of nuclear heating Roughly estimated MW of nuclear heating. Cryogenic load to remove nuclear heating ~ 4 MW e Other non-nuclear heat load to magnet? 10

11 Future Plan Check effect of shield LiPb coolant on radial build. Post new radial build on UW website: Optimize dimensions of local shield behind access tubes and confirm VV/magnet protection with 3-D analysis. 11

12 ARIES-CS Publications Submitted final manuscript to ICFRM-12 conference (Dec 4-9, 20, Santa Barbara): The Feasibility of Recycling and Clearance of Active Materials from Fusion Power Plants M. 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 Materials L. El-Guebaly, R. Forrest, T. Marshall, N. Taylor, K. Tobita, M. Zucchetti, Available at: 12