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

Transcription

1 DCLL Blanket for ARIES-AT: Major Changes to Radial Build and Design Implications L. El-Guebaly Fusion Technology Institute UW - Madison ARIES-Pathways Project Meeting December 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. 2

3 ARIES-AT Reference Design Fusion Power Major Radius Minor Radius Peak IB, OB, Div 1755 MW 5.2 m 1.3 m 3.1, 4.8, 2 MW/m2 SiC/SiC Composite Structure LiPb/SiC Blanket Discrete LiPb Manifolds HT S/C K No W on FW Calculated Overall TBR 1.1 ηth ~ 60% Availability 85% Plasma Control: 5 W Shells on IB and OB 2 Vertical Position Coils 2 Feedback Coils 3

4 Vacuum Vessel Vacuum Vessel (not reweldable) ARIES-AT Radial Builds: IB, OB, Div (SiC Structure) Th. Insulation 2 24 HT Shield 4 cm Vertical Stabilizing Shell 4 cm Vertical Stabilizing Shell Inboard 1 35 FW/Blanket 5 cm SOL Plasma + Th. Insulation Vacuum Vessel (not reweldable) Plasma SOL FW/Blanket-I 4 cm Vertical Stabilizing Shell 1 cm RWM Shell 4 cm Vertical Stabilizing Shell Blanket-II HT Shield Outboard + Th. Insulation 4 HT Shield HT Shield (replaceable) Divertor System Divertor cm

5 ARIES-AT Vacuum Vessel (FS Structure) 2 cm plate 2 cm (0.787"), Ty p B 2 cm rib 2 cm (0.787"), Ty p 2 cm plate 2 cm (0.787"), Ty p 3-D Cutway View of Vacuum Vessel IB and Top/Bottom VV Notes: Area for plumbing connections is as a step, but are local cuttouts Ribs are not shown(not-reweldable) Structure will be welded as required to form complete assembly View B - Rib Detail (10 x view) Dimension and Composition 40 cm IB VV: 13% FS, 22% H 2 O, 65% WC Filler 40 cm T/B VV:13% FS, 22% H 2 O, 65% B-FS Filler 25 cm OB VV: 30% FS, 70% H 2 O. 5

6 ARIES-AT TF/PF Magnet (High-Temp K) Winding Pack Sliver Composition: 7% YBCO 7% CeO 2 insulator 72% Inconel % Ag 13.5% GFF Polyimide insulator. YBCO CeO 2 Inconel-625 Structure Conduction cooling of WP from coil case. Coil case contains 5% LN cooling channels. 6

7 ARIES-AT Blanket Options SiC Structure FS Structure 3.8 cm FW Breeding Zone-I 1.5 cm FS/He 1.5 cm FS/He Breeding Zone-II 5 cm Back Wall 0.5 cm SiC Insert Reference ARIES-AT OB Blanket Breeder Coolant Structure LiPb LiPb SiC ARIES-AT-DCLL Blanket (a la ARIES-CS) Breeder Coolant Structure LiPb He and LiPb FS 7

8 ARIES-AT Compositions ARIES-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 8

9 ARIES-AT Radiation Limits and Key Parameters Calculated Overall TBR 1.1 Net TBR ~1.01 (for T self-sufficiency) Damage to Structure 3% Burnup - SiC/SiC composites (for structural integrity) 200 dpa - advanced FS Helium VV 1 He appm (for reweldability of FS) HT S/C TF & PF Magnets (@ K): Peak Fast n fluence to YBCO (E n > 0.1 MeV) n/cm 2 Peak Nuclear heating high Peak Dose to GFF Polyimide insulator < rads Plant Lifetime 40 FPY Availability 85% Operational Dose to Workers and Public < 2.5 mrem/h 9

10 Changes and Updates ARIES-AT-LiPb/SiC ARIES-AT-DCLL * (Reference Design) Peak IB, OB, Div 3.1, 4.8, 2 MW/m 2 3.1, 4.8, 2 MW/m 2 (to be updated) FS structure ORNL FS MF82H FS LiPb: Li enrichment 90% 90% Average temp 700 o C 580 o C Density 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

11 Vacuum Vessel Vacuum Vessel (not reweldable) IB Radial Build (3.1 MW/m 2 Peak NWL) Th. Insulation HT SiC Shield 4 cm Vertical Stabilizing Shell 4 cm Vertical Stabilizing Shell FW/Blanket (LiPb/SiC) SOL Plasma ARIES-AT Reference IB-RB 1 cm Th. Insulation HT FS Shield FW/Blanket (LiPb/He/FS) SOL Plasma ARIES-AT-DCLL IB-RB-I B/S contain ~8 cm He 11

12 IB Breeding & Radiation Damage (Replacing IB Shield by Blanket) IB Contribution to Overall TBR 90% 6 Li Enrichment IB Blanket Thickness (cm) 24 HT FS Shield 60 cm 36 FW/Blanket (LiPb/He/FS) 45 cm IB Blanket does not protect shield for 40 FPY Peak dpa at IB Shield 40 FPY) Limit IB Blanket Thickness (cm) He Production at IB VV 40 FPY) IB VV is not reweldable Limit IB Blanket Thickness (cm) Fast Neutron Fluence at Magnet (10 19 n/cm 40 FPY) More shield needed to protect magnet Limit IB Blanket Thickness (cm) cm blanket along with 20 cm shield (65 cm total) protects magnet

13 Vacuum Vessel (not reweldable) Vacuum Vessel 1 cm Recommended ARIES-AT-DCLL IB Radial Build (no LiPb/He Manifolds; no W Shells) Th. Insulation HT FS Shield FW/Blanket (LiPb/He/FS) SOL Plasma ARIES-AT-DCLL IB-RB-I 6 cm Th. Insulation HT FS Shield (replaceable) FW/Blanket (LiPb/He/FS) SOL Plasma Recommended IB RB ARIES-AT-DCLL No LiPb/He Manifolds No W Shells 13

14 Vacuum Vessel Vacuum Vessel OB Radial Build (4.8 MW/m 2 Peak NWL) Plasma SOL FW/Blanket-I (LiPb/SiC) 4 cm Vertical Stabilizing Shell 1 cm RWM Shell 4 cm Vertical Stabilizing Shell Blanket-II (LiPb/SiC) HT SiC Shield + Th. Insulation ARIES-AT Reference OB-RB 166 cm Plasma SOL FW/Blanket (LiPb/He/FS) HT FS Shield + Th. Insulation ARIES-AT-DCLL OB-RB-I B/S contain ~10 cm He

15 Calculated TBR Should be % 6 Li Enrichment OB TBR IB Blanket Thickness (cm) 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. 15

16 OB Breeding & Radiation Damage (Replacing OB Shield by Blanket) OB Contribution to Overall TBR 90% 6 Li Enrichment OB Blanket Thickness (cm) 91 cm 76 FW/Blanket (LiPb/He/FS) 15 HT FS Shield Peak dpa at OB Shield 40 FPY) OB Shield is overprotected OB Blanket Thickness (cm) Limit More OB shield needed for reweldability of VV More shield needed to protect magnet He Production at OB VV 40 FPY) OB Blanket Thickness (cm) Limit Fast Neutron Fluence at Magnet (10 19 n/cm 40 FPY) Limit OB Blanket Thickness (cm) cm blanket along with 20 cm shield (100 cm total) protects VV and magnet

17 Vacuum Vessel Vacuum Vessel Recommended ARIES-AT-DCLL OB Radial Build (no LiPb/He Manifolds; no W Shells) 166 cm Plasma SOL FW/Blanket (LiPb/He/FS) HT FS Shield + Th. Insulation ARIES-AT-DCLL OB-RB-I 175 cm Plasma SOL FW/Blanket (LiPb/He/FS) HT FS Shield + Th. Insulation Recommended OB RB ARIES-AT-DCLL No LiPb/He Manifolds No W Shells 17

18 Divertor Radial Build (2 MW/m 2 Peak NWL) Th. Insulation Vacuum Vessel (not reweldable) HT SiC Shield HT SiC Shield (replaceable) Divertor System ARIES-AT Reference D-RB cm cm w/o gaps 18 + Th. Insulation Vacuum Vessel 40 HT FS Shield 30 Divertor System 3 20 ARIES-AT-DCLL 2 D/S contain ~16 cm He D-RB-I

19 Divertor Radiation Damage (Adding Replaceable Shield) 18 cm Replaceable shield protects permanent shield Peak dpa at Permanent Shield 40 FPY) Limit Replaceable Shield Thickness (cm) He Production at VV 40 FPY) 40 cm Thick permanent shield needed for reweldability of VV cm Permanent Shield Limit Replaceable Shield Thickness (cm) Magnet is over protected Fast Neutron Fluence at Magnet (10 19 n/cm 40 FPY) cm Permanent Shield 40 cm VV Limit Replaceable Shield Thickness (cm) 18 cm replaceable shield and 40 cm permanent shield protect VV. Shield and 27 cm VV protect magnet. 19

20 Recommended ARIES-AT-DCLL Divertor Radial Build (no LiPb/He Manifolds) cm w/o gaps + Th. Insulation Vacuum Vessel (not reweldable) HT FS Shield cm w/o gaps + Th. Insulation Vacuum Vessel (reweldable) HT FS Shield HT FS Shield (replaceable) 18 3 Divertor System 20 Divertor System 20 ARIES-AT-DCLL D-RB-I 20 Recommended Div RB ARIES-AT-DCLL No LiPb/He Manifolds

21 Radiation Level IB OB Div. Limit Peak NWL (MW/m 2 ) dpa at shield 40 FPY): 200 Replaceable Permanent --- # He production at manifolds (He 40 FPY) He production at VV (He 40 FPY) 19 ** K: Fast neutron fluence (10 19 n/cm 40 FPY) Nuclear heating (mw/cm 3 ) * 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. 21

22 Impact of DCLL System on ARIES-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 FW/blanket lifetime 4 FPY 2.8 FPY Overall energy multiplication 1.1 ~1.15 Structure unit cost (2004 $) 510 $/kg 103 $/kg η th ~ 60% 40-45% Cost of heat transfer/transport system $126M > $300M (1992 $) He pumping power --- > 100 MW e 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 22

23 Observations and Questions Observations: 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 Nb 3 Sn magnet? Impact of new shell location (outside sizable IB and OB blankets) on beta and other physics parameters? 23