Preliminary ARIES-RS-DCLL Radial Build for ASC

Transcription

1 Preliminary ARIES-RS-DCLL Radial Build for ASC L. El-Guebaly Fusion Technology Institute University of Wisconsin - Madison Contributors: C. Kessel (PPPL), S. Malang, R. Raffray (UCSD) ARIES-Pathways Project Meeting May 28-29, 08 UW - Madison

2 Objectives Define preliminary radial builds for ARIES-RS with: DCLL blanket and shield LiPb/He Manifolds (tentative composition/dimension/location) Stabilizing shells. Identify potential locations for stabilizing shells and feedback coils and assess impact on TBR, if any. Compare reference ARIES-RS with ARIES-RS-DCLL and highlight impact of DCLL system on overall design. 2

3 ARIES-RS Reference Design 3

4 ARIES-RS Reference Design (Cont.) Fusion Power 2167 MW Major Radius 5.52 m Minor Radius 1.38 m Peak IB, OB, Div 3.7, 5.6, 2.3 MW/m 2 V-4Cr-4Ti Structure Li/V Blanket 2.5, 7.5, and 40 FPY Components Discrete Li Manifolds LT S/C 4 k No W on FW Calculated Overall TBR 1.1 η th 46% Availability 76% Plasma Control: 5 cm W Shells on IB 6 cm W Shells on OB 2 cm V Kink Shell behind OB FW 4

5 Design Requirements Calculated Overall TBR * 1.1 Net TBR * (for T self-sufficiency) ~1.01 Damage to Structure 0 dpa - advanced FS (for structural integrity) or V Helium Manifolds and VV 1 He appm (for reweldability of FS) LT S/C Magnet (@ 4 K): Peak Fast n fluence to Nb 3 Sn (E n > 0.1 MeV) n/cm 2??????????? Peak Nuclear heating 2 mw/cm 3 Peak dpa to Cu stabilizer 6x10-3 dpa Peak dose to electric insulator < rads Plant Lifetime 40 FPY Availability 85% Operational Dose to Workers and Public < 2.5 mrem/h 5

6 Vacuum Vessel Vacuum Vessel ARIES-RS Radial Builds: IB, OB, Div (V Structure, Li Breeder, Li/He Coolants) Plasma Inboard SOL 2 cm V Kink Shell SS Jacket, Insulator, + Th. Insulation FW/Blanket-I Blanket-II 2 28 LT Shield Reflector 2 26 HT Shield 6 cm Vertical Stabilizing Shell HT Shield 6 cm Vertical Stabilizing 6 cm Vertical Shell Stabilizing Shell 5 cm Vertical Stabilizing Shell 5 cm Vertical Stabilizing Shell 1 HT Shield (replaceable) LT Shield Outboard 1.3 FW/Blanket 5 cm SOL Plasma + Th. Insulation SS Jacket, Insulator, 6 SS Jacket, Insulator, + Th. Insulation Vacuum Vessel LT Shield HT Shield Structural Ring Divertor System Divertor > 2 > > 2 5 cm

7 Changes, Updates, and Assumptions ARIES-RS-Li/V (Reference Design) ARIES-RS-DCLL Peak IB, OB, Div 3.7, 5.6, 2.3 MW/m 2 3.7, 5.6, 2.3 MW/m 2 7 (to be updated) Structure V-4Cr-4Ti and Tenelon MF82H FS Breeder and Enrichment Li LiPb natural 90% (or less) OB blanket Two segments One segment? W shells: Two 5-cm-thick W VS shells on IB: Between IB HT shield Segments Between IB blanket & shield? (toroidally continuous) Two 6-cm-thick W VS shells on OB: Between OB blanket & HT Shield Behind OB blanket? (toroidally continuous) kink shell: 2-cm-thick V Behind OB FW Thin Cu shell behind OB FW? (discrete) Breeder/coolant manifolds Discrete Toroidally continuous: 25 cm He/LiPb manifolds for IB blanket & shield 35 cm He/LiPb manifolds for OB blanket & shield cm He manifolds for divertor shield HT Shield coolant Li He LT Shield coolant He --- VV coolant He H 2 O s between HT components 2 cm --- VV model Homogeneous Heterogeneous with 2-cm-thick plates Cross section data library IAEA FENDL-2 IAEA FENDL-2.1

8 Vacuum Vessel Manifolds (not Midplane) Vacuum Vessel Recommended ARIES-RS-DCLL IB Radial Build (Peak Γ = 3.7 MW/m 2 ) SS Jacket, Insulator, + Th. Insulation SS Jacket, Insulator, + Th. Insulation cm w/o gaps LT Shield cm W VS Shell 2 26 HT Shield HT FS Shield (replaceable every 12 FPY) 185 cm w/o gaps 5 cm W VS Shell 5 cm Vertical Stabilizing 5 cm W VS Shell 1 HT Shield (replaceable every 7.5 FPY) 1 45 FW/Blanket (LiPb/He/FS) (replaceable every 3 FPY).3 FW/Blanket (replaceable every 2.5 FPY) 47.3 cm 50 cm 8 5 cm SOL 5 SOL Plasma Plasma Reference ARIES-RS ARIES-RS-DCLL IB radial build increases by cm. Upper/lower W VS shells could be placed between blanket & shield (50 cm from plasma). Shells embedded in replaceable shield?! Shield will be segmented into replaceable and permanent components. Manifolds are reweldable at top/bottom, not around midplane.

9 Vacuum Vessel Vacuum Vessel Plasma Plasma SOL SOL * Cross section between magnets TBD. Recommended ARIES-RS-DCLL OB Radial Build (Peak Γ = 5.6 MW/m 2 ) (Cross Section through Magnet * ) cm V Kink Shell FW/Blanket-I (replaceable every 2.5 FPY) 214 cm w/o gaps cm Blanket-II (replaceable every 7.5 FPY) FW/Blanket (LiPb/He/FS) (replaceable every 3 FPY) 85 cm Reflector 6 cm VS Shell HT Shield 6 cm VS Shell LT Shield 6 cm VS Shell 6 cm VS Shell HT FS Shield LiPb/He Manifolds 219 cm w/o gaps + Th. Insulation SS Jacket, Insulator, Th. Insulation SS Jacket, Insulator, Reference ARIES-RS ARIES-RS-DCLL OB radial build increases by 5-7 cm. Upper/lower W VS shells could be placed between blanket & shield (85 cm from plasma). Feedback coils could be placed behind manifolds (140 cm from plasma).

10 Optimization of VV Composition and Thickness Peak Fluence (10 19 n/cm 40 FPY) or Peak Heating (mw/cm 3 ) 10-1 Inboard VV 10 3 cm Thick VV 10 2 Heating Fluence Heating Limit Fluence Limit 40% H 2 O 57% WC Water Content in IB VV (%) Replacing WC or B-FS with H 2 O Peak Fluence (10 19 n/cm 40 FPY) or Peak Heating (mw/cm 3 ) Outboard VV cm Thick VV Fluence Heating Heating Limit Fluence Limit 60% H O 2 23% B-FS Water Content in OB VV (%) Peak Fluence (10 19 n/cm 40 FPY) or Peak Heating (mw/cm 3 ) Fluence Fluence Limit IB VV 40% H 2 O 57% WC Heating Limit Heating IB VV Tickness (cm) 10 Peak Fluence (10 19 n/cm 40 FPY) or Peak Heating (mw/cm 3 ) % H 2 O 23% B-FS Heating Fluence Heating Limit 10 0 Fluence Limit OB VV OB VV Thicness (cm)

11 Recommended ARIES-RS-DCLL Divertor Radial Build (Peak Γ = 2.3 MW/m 2 ) SS Jacket, Insulator, Large + Th. Insulation > 2 SS Jacket, Insulator, 3.2 Large + Th. Insulation > Vacuum Vessel Large LT Shield > cm w/o gaps 178 cm w/o gaps Vacuum Vessel Large He Manifolds HT FS Shield > 2 40 HT Shield Structural Ring Divertor System 35 1 > 2 5 cm cm replaceable shield (every 6 FPY). cm He manifolds. Div radial build decreases by 1-5 cm. HT FS Shield (replaceable every 6 FPY) Divertor System (plates & He manifolds, a la ARIES-CS) 3 Reference ARIES-RS 11 ARIES-RS-DCLL

12 Potential Locations for Stabilizing Shells and Feedback Coils Distance from Plasma (cm) Reference ARIES-RS ARIES-RS-DCLL Vertical Stabilizing Shells: Inboard (between blanket and shield) 47 50? Outboard (between blanket and shield) 61 85? Kink Shells: Outboard 7 9 or 45? (behind OB FW) (behind OB FW or between blanket segments) Feedback Coils: Outboard ? (behind OB shield) (behind OB manifolds) 12

13 Kink Shell Behind OB FW? Could Cu (or W) kink shell be placed behind OB FW? Integration of kink shell with blanket? Impact on breeding? SOL 3.8 cm FW Breeding Zone - I 0.5 cm SiC Insert 1.5 cm FS/He 1.5 cm FS/He > 80 cm Breeding Zone - II 1.5 cm FS/He Breeding Zone - III 5 cm Back Wall Calculated Overall TBR Required Calculated TBR Cu? W? Shell Thickness (cm) Kink Shell 58% FS 42% He ARIES-RS-DCLL OB Blanket with kink shell behind FW IB and/or OB Blanket should be thickened to compensate for breeding losses 13

14 Kink Shell Between OB Blanket Segments? Could OB blanket be segmented into two segments? Benefits: Cu (or W) kink shell placed between OB blanket segments Less integration problems Less impact on breeding Lifetime of back segment > 3 FPY (~15 FPY) Notable reduction in lifecycle radwaste volume. If feasible, revisit ARIES-AT-DCLL? d/a ~ 0.35 for VS shells > 80 cm ARIES-RS-DCLL OB Blanket With Cu kink and VS shells between blanket segments (blanket Temp < 700 o C) SOL 3.8 cm FW Blanket-I Cu Kink Shell Blanket-II 5 cm Back Wall Cu VS Shell 14

15 Impact of DCLL System on ARIES-RS Overall Design Reference ARIES-RS ARIES-RS-DCLL IB, OB, Div radial standoff * 173, 214, , 219, 178 Limit for max NWL (m) ~ 6 < 5.5? R (m) 5.52 > 5.52 Overall energy multiplication 1.2 ~ 1.15 η th 46% 40 45% Structure unit cost # 300 $/kg of V ~ 60 $/kg of FS Blanket/divertor/shield/manifolds cost * ~ $80M < $80M Cost * of heat transfer/transport system $260M $ M Pumping power 12 MW e ~ 150 MW e LSA factor 2 2 Cost of Electricity # : 76 mills/kwh > 76 mills/kwh Maintenance approach Sector Maintenance? * Excluding gaps. # in 1992$. (with coolant pipes attached at bottom) 15

16 Observations, Future Work, and Needed Info Observations: DCLL system increases IB and OB radial standoff Kink shell degrades breeding Resistivity increases with neutron fluence. Impact on stabilizing shell parameters? To do: Adjust blanket dimensions to accommodate kink shell and estimate TBR for one OB blanket segment or two, if feasible Assess breeding potential with < 90% enrichment. This may require fairly thick IB and OB blankets. Impact on locations of vertical stabilizing shell and feedback coils? Divide IB shield into replaceable and permanent components to minimize radwaste stream Provide OB radial build for Xn between magnets for ASC Pay special attention to location and configuration of He-access pipes for upper/lower divertors Surround pumping ducts with penetration shield to limit radiation damage at VV and magnet. Need: Info on new fluence limit for Nb 3 Sn and reference Physics parameters for ARIES-RS-DCLL system to estimate peak IB and OB NWL Locations of kink shells, vertical stabilizing shells, and feedback coils Blanket composition Size, composition, and location of manifolds. 16