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1 ANS 16 th Topical Meeting on the Technology of Fusion Energy September 14 - 16, 2004 Madison, Wisconsin.

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Presentation on theme: "1 ANS 16 th Topical Meeting on the Technology of Fusion Energy September 14 - 16, 2004 Madison, Wisconsin."— Presentation transcript:

1 1 ANS 16 th Topical Meeting on the Technology of Fusion Energy September 14 - 16, 2004 Madison, Wisconsin

2 2 General Chair Technical Program Chair Gerald KulcinskiLaila El-Guebaly Paper submissions will be requested in all areas of MFE & IFE fusion technologies: - Engineering of experimental devices - Power plant studies - High heat flux components - IFE target fabrication, injection, and tracking - In-vessel components (blanket, shield, vacuum vessel) - IFE chamber dynamics and clearing - Magnets - Nuclear analysis and experiments (neutronics, shielding, and activation) - Structural and breeding materials - Material and component test facilities - Blanket testing - Safety and environment - Radwaste management - Tritium handling and processing - Plasma engineering, heating, and control - Diagnostics - Fabrication, assembly, and maintenance - Power conversion and conditioning - Computational tools and validation experiments - Alternate, non-electric applications of fusion - Hydrogen production - Socioeconomics.

3 Radial Build Definition for LiPb/FS and Li/FS Systems Laila El-Guebaly Fusion Technology Institute University of Wisconsin - Madison With Input from: S. Malang (FZK) and R. Raffray (UCSD) http://fti.neep.wisc.edu/FTI/ARIES/SEP2003/lae_radialbuild.pdf ARIES-CS Project Meeting September 3, 2003 Atlanta, GA

4 4 Net Electric Power 1000 MW e Fusion Power2000 MW # of Field Periods 3 A 4.5 8.25 m 1.85 m Average Neutron Wall Loading (  )* 2 MW/m 2 FW Area~ 800 m 2 Toroidal Length of Field Period~ 9 m Minimum Plasma to Mid-Coil Distance (  min )1.2 m # of  min per Field Period2 FW Coverage Fraction # for Shield-only Zones8% Initial Parameters (1/31/03 Strawman - L.P. Ku) _____________________________ * Peak  is ~3 MW/m 2. # Sensitive to difference between  min and nominal .

5 5 Overall TBR1.1 (for T self-sufficiency) dpa to FS Structure200 dpa (for structural integrity) Helium Production @ VV1 appm (for reweldability of FS) LT S/C Magnet (@ 4K): n fluence to Nb 3 Sn (E n > 0.1 MeV)10 19 n/cm 2 Dose to polyimide insulator 10 11 rads Nuclear heating 2mW/cm 3 dpa to Cu stabilizer6x10 -3 dpa Biological dose outside building 2.5 mrem/h (dose during operation for workers and public protection) Design Requirements and Radiation Limits

6 6 Peak to average  = 1.5 RF Penetrations and assembly gaps occupy 2% of FW area. Divertor plates/baffles: –5 cm thick –50% structure and 50% He coolant –Cover 15% of FW area. SPPS magnet composition. 8% FW coverage fraction of shield-only zones used for all blanket concepts. 1-D poloidal neutronics model with av. a = 1.85 m. Assumptions

7 7 BreederMultiplierStructureBlanket/ShieldVVVV CoolantCoolantLocation ARIES-CS: FlibeBeFSFlibeH 2 OInside Magnet LiPb–SiCLiPb H 2 OInside Magnet LiPb–FSHe H 2 OInside Magnet LiPb–FSHe HeOutside Magnet Li–FSHe HeOutside Magnet SPPS: Li–VLiHe Outside Magnet Candidate Blanket Concepts

8 8 Coil Case & Support Structure Recommended LiPb/FS/He Radial Build (water-cooled internal VV) SOL Vacuum Vessel FS Shield Gap Thickness (cm) FW Gap + Th. Insulator Winding Pack Plasma 5 4.8 2 ≥ 2 3220 2.2 28  ≥ 143 cm | | SOL Vacuum Vessel Back Wall Gap Thickness (cm) Gap + Th. Insulator Coil Case & Insulator Winding Pack Plasma 5 2 2 47 202.2 28 || Coil Case & Insulator Coil Case & Support Structure  min = 112 cm Shield Only Zones Blanket (LiPb/FS/He) 47 11 WC Shield Blanket Zones Back Wall 9 1 Gap FW 4.8 Boundary between WC-shield and back wall will be adjusted to meet design requirements

9 9 ComponentsComposition FW31% FS Structure 69% He Coolant Blanket90% LiPb with 90% enriched Li 3% FS Structure 7% He Coolant WC Shield * 90% WC Filler 3% FS Structure 7% He Coolant FS Shield15% FS Structure 10% He Coolant 75% Borated Steel Filler VV28% FS Structure 49% Water 23% Borated Steel Filler Winding Pack25% Incoloy Structure (Composition not available. Used SPPS’) 20% Cu Stabilizer 15% Nb 3 Sn + Conduit 25% GFF Polyimide 15% LHe LiPb/FS/He System (water-cooled internal VV) _______________ * Same constituents for blanket with WC replacing LiPb.

10 10 Cryostat, Coil Case, Support Structure Recommended LiPb/FS/He Radial Build (He-cooled External VV) SOL Vacuum Vessel FS Shield Thickness (cm) FW Gap + Th. Insulator Winding Pack Plasma 5 4.8 ≥ 2 89 20 10.2  ≥ 178 cm | | SOL Back Wall Gap Thickness (cm) Gap + Th. Insulator Cryostat, Coil Case, Insulator Winding Pack Plasma 5 1 26 47 20 10.2 || Cryostat, Coil Case, Insulator Cryostat, Coil Case, Support Structure  min = 115 cm Shield Only Zones Blanket (LiPb/FS/He) 47 9 WC Shield-I Blanket Zones Back Wall 9 1 Gap FW 4.8 Vacuum Vessel WC Shield-II 2 Boundary between WC-shield and back wall will be adjusted to meet design requirements

11 11 ComponentsComposition FW31% FS Structure 69% He Coolant Blanket90% LiPb with 90% enriched Li 3% FS Structure 7% He Coolant WC Shield-I * 90% WC Filler 3% FS Structure 7% He Coolant WC Shield-II # 15% FS Structure 10% He Coolant 75% WC Filler FS Shield15% FS Structure 10% He Coolant 75% Borated Steel Filler Winding Pack25% Incoloy Structure (Composition not available. Used SPPS’) 20% Cu Stabilizer 15% Nb 3 Sn + Conduit 25% GFF Polyimide 15% LHe VV30% FS Structure 70% He LiPb/FS/He System (He-cooled External VV) _______________ * Same constituents for blanket with WC replacing LiPb. # Same constituents for FS-shield with WC replacing B-FS filler. ZrH 1.7 filler could save 2-3 cm in radial build.

12 12 Cryostat, Coil Case, Support Structure Recommended Li/FS/He Radial Build (He-cooled External VV) SOL Vacuum Vessel FS Shield Thickness (cm) FW Gap + Th. Insulator Winding Pack Plasma 5 4.8 ≥ 2 94 20 10.2  ≥ 197 cm | | SOL Back Wall Gap Thickness (cm) Gap + Th. Insulator Cryostat, Coil Case, Insulator Winding Pack Plasma 5 2 10 62 20 10.2 || Cryostat, Coil Case, Insulator Cryostat, Coil Case, Support Structure  min = 113 cm Shield Only Zones Blanket (Li/FS/He) 62 8 WC Shield-I Blanket Zones Back Wall 8 1 Gap FW 4.8 Vacuum Vessel WC Shield-II 1 Boundary between WC-shield and back wall will be adjusted to meet design requirements

13 13 ComponentsComposition FW31% FS Structure 69% He Coolant Blanket90% Li (natural) 3% FS Structure 7% He Coolant WC Shield-I * 90% WC Filler 3% FS Structure 7% He Coolant WC Shield-II # 15% FS Structure 10% He Coolant 75% WC Filler FS Shield15% FS Structure 10% He Coolant 75% Borated Steel Filler Winding Pack25% Incoloy Structure (Composition not available. Used SPPS’) 20% Cu Stabilizer 15% Nb 3 Sn + Conduit 25% GFF Polyimide 15% LHe VV30% FS Structure 70% He Li/FS/He System (He-cooled External VV) _______________ * Same constituents for blanket with WC replacing LiPb. # Same constituents for FS-shield with WC replacing B-FS filler. ZrH 1.7 filler could save 2-3 cm in radial build.

14 14 Nominal Blanket and Shielding Components ARIES-CS SPPS Internal VV External VV External VV Blanket ConceptFlibe/FS/BeLiPb/SiCLiPb/FS/HeLiPb/FS/HeLi/FS/HeLi/V Thickness (cm): FW/Blanket-I3325525267 36 Gap–1–––– FW/Blanket-II–25–––– FS Back Wall––998– Gap1–1112 HT Shield453532899445 Gap222––2 LT Shield –––––35 VV 252528––– Total B/S/VV 106113124151170120 Net Change- 14- 7+ 4+ 31+ 50– (compared to SPPS)

15 15 Nominal Plasma to Mid-Coil Distance ARIES-CS SPPS Internal VV External VV External VV Blanket ConceptFlibe/FS/BeLiPb/SiCLiPb/FS/HeLiPb/FS/HeLi/FS/HeLi/V Thickness (cm): SOL5555515 FW/B/S/VV106113124151170 120 Gap + Th. Insl. ≥ 2 ≥ 2 ≥ 2 ≥ 2 ≥ 2 ≥ 8 Cryostat * 2.2 2.2 2.2 10.210.215 1/2 Winding Pack 101010101038  125132143178197196 Net Change- 71- 64- 53- 18+ 1– (compared to SPPS) ___________________________ * Includes coil case and electric insulator. Flibe system offers most compact radial build

16 16 Comparison Between Nominal Radial Builds Water-cooled internal VV helps reduce nominal radial build

17 17 Recommended Shield-Only Zones for  min ARIES-CS SPPS Internal VV External VV External VV Blanket ConceptFlibe/FS/BeLiPb/SiCLiPb/FS/HeLiPb/FS/HeLi/FS/HeLi/V Thickness (cm): WC Shield-I3325525267 – FS Back Wall––1198– Gap11–11– WC Shield-II2536–2610– Gap222––– LT Shield –––––– VV 252528––– Total B/S/VV 8689938886

18 18 Dimensions of  min Shielding Components (no Blanket) ARIES-CS SPPS Internal VV External VV External VV Blanket ConceptFlibe/FS/BeLiPb/SiCLiPb/FS/HeLiPb/FS/HeLi/FS/HeLi/V Thickness (cm): SOL55555– FW/B/S/VV8689937886– Gap + Th. Insl. ≥ 2 ≥ 2 ≥ 2 ≥ 2 ≥ 2 – Cryostat * 2.2 2.2 2.2 10.210.2– 1/2 Winding Pack 1010101010–  min 105108112115113 ___________________________ * Includes coil case and electric insulator.  min varies slightly with blanket concept

19 19 Comparison Between  min (Shield-Only Zones, no Blanket) VV location has negligible impact on  min Blanket & Shield

20 20 Comparison Between Radial Builds ARIES-CS SPPS Internal VV External VV External VV Blanket ConceptFlibe/FS/BeLiPb/SiCLiPb/FS/HeLiPb/FS/HeLi/FS/HeLi/V Thickness (cm): Nominal  125132143178197196  min (shield-only) 105108112115113– Net Saving20243163 ?84 ?– Shield-only zones could offer 20 - 84 cm (16 - 43%) reduction in radial build. Net saving exceeding 20 cm calls for shield-only zones with FW coverage > 8%, meaning overall TBR < 1.1. It is impossible to achieve TBR of 1.1 for LiPb and Li systems if shield-only zones cover 30-40% of FW area. Potential solutions: – For internal VV case, thicken LiPb blanket – For external VV case, install LiPb (or Li) blanket everywhere with uniform or variable thickness.

21 21  min Occurs Twice per Field Period Normalized Toroidal Angle (N p  /2  ) Normalized Poloidal Angle (  /2  )  min = 1.2 m 6 Locations for  min Middle of Field Period Beginning of Field Period End of Field Period

22 22 Transition Region for  of 1.2-1.4 m Covers ~8% of FW Area Normalized Toroidal Angle Normalized Poloidal Angle Blanket/Shield Shield-only Zone Coverage Fraction Shield-only zone 8% Blanket/Shield 92%

23 23 Transition Region for  of 1.2-2.0 m Covers ~40% of FW Area Normalized Toroidal Angle Normalized Poloidal Angle Blanket/Shield Shield-only Zone Blankets may not provide TBR ≥ 1.1 if coverage fraction drops below 70% Coverage Fraction Shield-only zone 40% Blanket/Shield 60% Blanket/Shield

24 24 Potential Solution for Sizable Transition Regions Normalized Toroidal Angle Normalized Poloidal Angle Uniform Blanket/Shield Shield-only Zone Blanket with variable thickness could meet breeding requirement Coverage Fraction Shield-only zone ~1% Non-uniform Blanket/Shield 39% Uniform Blanket/Shield 60% Uniform Blanket/Shield Shield-only Zone Non-uniform Blanket/Shield

25 25 WC-Shield-Only Zones for  min Introduce Engineering Problems Benefits: –Compact radial build –Smaller R and lower B max – Lower COE Potential engineering problems: – Integration of WC-shield with blanket system – Accommodation of WC decay heat removal loop – Heavy WC shield  many small modules, if weight-limited – Any WC high level waste?

26 26 Key Parameters for ARIES-CS System Analysis Flibe/FS/BeLiPb/SiCLiPb/FSLi/FS TBR1.11.11.1 * ? 1.1 * ? Energy Multiplication (M n )1.21.11.151.13 Thermal Conversion Efficiency (  th )45%55-60% ??% ??% FW Lifetime (FPY)6.565 7 System Availability~80%~80% ~80% ~80% Integrated system analysis could assess impact of M n and  th on COE for comparable  min ___________________________ * Based on 8% FW coverage fraction for shield-only zones.

27 27 Conclusions Radial standoff controls COE, a unique feature for stellarators. Employ expensive, highly efficient shield at  min and combine blanket and cheap shield elsewhere, if difference in radial builds ≤ 30 cm. Blankets should breed extra tritium to compensate for losses due to non- breeding shield-only zones. To reduce  min, use: – WC-shield – Liquid breeder to cool HT shield – Water to cool LT shield (or internal VV) – No He coolant for shield. Shield-only  min varies slightly (2-7 cm) with blanket concept. External VV increases  min by few cm. Economic impact of shield-only zones needs to be assessed and innovative solutions to WC problems should be developed.

28 28 Conclusions (cont.) For water-cooled internal VV case, Flibe system offer most compact radial build, followed by LiPb. For external VV case, LiPb and Li blankets should be installed everywhere to meet breeding requirement. Water is superior shielding material that helps reduce nominal radial build and minimize radwaste volume  Exclude breeders incompatible with water. 3-D nuclear analysis is needed to: – Generate neutron wall loading profile using CAD-MCNP interface * – Assess 3-D impact of shield-only zones on breeding – Determine 3-D effect of penetrations, assembly gaps, and divertor system on TBR – Evaluate overall TBR for blankets with variable thickness –Confirm key nuclear parameters (M n, lifetime,  min, etc) – Determine boundary between replaceable and permanent components. _______________ * Under development at UW.

29 29 9 Xns of Plasma Boundary (red) and WP Center (green) Covering Half Field Period (~9 m)  max ~ 4.6 m  peaks @ ~3 MW/m 2 at black dot  min = 1.2 m Middle of Field Period End of Field Period

30 30 Transition Region Between  min and  min + 0.2 m Covers ~8% of FW Area  min = 1.2 m Blue areas: ~2 m Poloidal extent ~5.5 m Toroidal extent ~8% of FW area Middle of Field Period End of Field Period

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