ARIES AT Project Meeting - Princeton, NJ 18 Sept 00 1 ARIES-AT Toroidal Field (TF) and Poloidal Field (PF) Coils Tom Brown, Fred Dahlgren, Phil Heitzenroeder.

Slides:



Advertisements
Similar presentations
Superconducting Magnet Program S. Gourlay CERN March 11-12, Lawrence Berkeley National Laboratory IR Quad R&D Program LHC IR Upgrade Stephen A.
Advertisements

AT Pilot Plant EM and Structural Studies P. Titus.
September 15-16, 2005/ARR 1 Status of ARIES-CS Power Core and Divertor Design and Structural Analysis A. René Raffray University of California, San Diego.
Update on ARIES-CS Coil Structural Analysis X.R. Wang and A.R. Raffray ARIES Meeting PPPL, NJ October 4-5, 2006.
MUTAC Review, 9 April MuCOOL and MICE Coupling Magnet Status Michael A. Green Lawrence Berkeley Laboratory Berkeley CA
1 1. Cover Page S. NISHIO Japan Atomic Energy Agency, Naka Fusion Institute, Naka-shi, Ibaraki-ken , Japan US - Japan.
1 Configuration Development for HIF Final Focus Superconducting Quadrupole Array HIF Final Focus Meeting July 2, 2002 Tom Brown Chang Jun Phil Heitzenroeder.
Preliminary Analysis of the Target System Magnets 1.Version with a 6-T copper magnet insert 2.Version with a 6-T high-temperature superconductor insert.
Magnet System Definition L. Bromberg P. Titus MIT Plasma Science and Fusion Center ARIES meeting November 4-5, 2004.
ARIES Review, PPPL L. M. Waganer, 4-5 Oct 2006 Summary of Low Cost Fabrication of Integrated Coil Structure L. M. Waganer With Support from Kevin Slattery.
Development of the New ARIES Tokamak Systems Code Zoran Dragojlovic, Rene Raffray, Farrokh Najmabadi, Charles Kessel, Lester Waganer US-Japan Workshop.
Status of the Coil Structure Design and Magnetic-Structural Analysis Presented by X.R. Wang Contributors: UCSD: S. Malang, A.R. Raffray PPPL: H.M. Fan.
ARIES-Stellerator studies Magnet issues L. Bromberg P. Titus MIT Plasma Science and Fusion Center Cambridge MA May 7, 2003.
Progress on Engineering and Costing Algorithms for ARIES Systems Code Zoran Dragojlovic, Rene Raffray, Chuck Kessel and Leslie Bromberg ARIES Project Meeting.
HTS Magnets for ARIES-AT L. Bromberg J.H. Schultz MIT Plasma Science and Fusion Center ARIES Meeting March 20, 2000.
Stellarator magnets L. Bromberg J.H. Schultz MIT Plasma Science and Fusion Center ARIES meeting March 8-9, 2004.
June19-21, 2000Finalizing the ARIES-AT Blanket and Divertor Designs, ARIES Project Meeting/ARR ARIES-AT Blanket and Divertor Design (The Final Stretch)
Magnet considerations for ARIES IFE L. Bromberg With contributions from J.H. Schultz MIT Plasma Science and Fusion Center ARIES Meeting Madison, WI September.
March 20-21, 2000ARIES-AT Blanket and Divertor Design, ARIES Project Meeting/ARR Status ARIES-AT Blanket and Divertor Design The ARIES Team Presented.
NCSX NCSX Planar Coil "ASIPP" Presentation 1 December 8-10, 2005 Michael Kalish NCSX TF and PF Coils.
Superconducting Large Bore Sextupole for ILC
ASIPP EAST Overview Of The EAST In Vessel Components Upgraded Presented by Damao Yao.
Kanwalpreet Kaur Communication subsystem & Integration subsystem.
Joint Institute for Nuclear Research Further optimization of the solenoid design A.Efremov, E.Koshurnikov, Yu.Lobanov, A.Makarov, A.Vodopianov GSI, Darmstadt,
NSTX Center Stack Upgrade Workshop Requirements & Design Point C Neumeyer Jan 22, 2009.
KDEMO Structural Analysis P. Titus June ! KDEMO coil axisymmetric analysis pfcb 21 1, 1.52,0.70,.9,1.3,8,10 !CS1 2, 1.52,2.10,.9,1.3,8,10 !CS2.
Neutronics Analysis for K-DEMO Blanket Module with Helium coolant June 26, 2013 Presented by Kihak IM Prepared by Y.S. Lee Fusion Engineering Center DEMO.
1 WBS 1 Design Analysis Status NCSX Analysis Meeting Dec 3, 2003.
U PDATED ARIES-ACT P OWER C ORE D EFINITION AND S I C B LANKET X.R. Wang, M. S. Tillack, S. Malang F. Najmabadi and L.A. El-Guebaly ARIES-Pathways Project.
Systems Code – Hardwired Numbers for Review C. Kessel, PPPL ARIES Project Meeting, July 29-30, 2010.
HT-7U CASIPP 1 The Engineering Design of the Poloidal Field System of HT-7U Tokamak PF Group of HT-7U Team Chinese Academy of Sciences, Institute of Plasma.
NCSX Vacuum Vessel Stress Analysis FDR Fred Dahlgren 17 May 2004.
Stabilizing Shells in ARIES C. E. Kessel Princeton Plasma Physics Laboratory ARIES Project Meeting, 5/28-29/2008.
Magnet for ARIES-CS Magnet protection Cooling of magnet structure L. Bromberg J.H. Schultz MIT Plasma Science and Fusion Center ARIES meeting UCSD January.
Results of Linear Stress Analyses for Modular Coils and Coil structure For 2T High Beta Currents at 0 Seconds and Initial Coil Shrinkage of in/in.
Superconducting Magnet Group Superconducting magnet development for ex-situ NMR LDRD 2003 Paolo Ferracin, Scott Bartlett 03/31/2003.
R EFINEMENT OF THE P OWER C ORE C ONFIGURATION OF THE ARIES-ACT SA X.R. Wang 1, M. S. Tillack 1, S. Malang 2 and F. Najmabadi 1 1 University of California,
ARIES-CS Power Core Configuration Presented by X.R. Wang Contributors: Laila A. Ei-Guebaly, S. Malang, T.K. Mau, Richard Peiperty, A.R. Raffray and L.
Systems Analysis Development for ARIES Next Step C. E. Kessel 1, Z. Dragojlovic 2, and R. Raffrey 2 1 Princeton Plasma Physics Laboratory 2 University.
Muon Cooling Channel Superconducting Magnet Systems Muon Collider Task Force Meeting on July 31, 2006 V.S. Kashikhin.
CERN Accelerator School Superconductivity for Accelerators Case study 3 Paolo Ferracin ( ) European Organization for Nuclear Research.
NCSX NCSX Preliminary Design Review1 Conventional Coils and Structure Phil Heitzenroeder, Len Myatt, and Mike Viola for the NCSX Engineering Team.
Nonlinear Analyses of Modular Coils and Shell structure for Coil Cool-down and EM Loads Part 1 – Results of Shell Structure and Modular Coils H.M. Fan.
1 PFC requirements  Basic requirements  Carbon based  Provisions for adding (interface design included in research prep budget)  NBI armor  Trim coil.
AWB NSTX TF Flag Joint Design Review April 10, 2003 Art Brooks.
A View of NCSX Structural System and Load Path for the Base Support Structure.
Open house 2013 slides T. Brown. 1.6-m FNSF Super-X Divertor Configuration.
NCSX NCSX TF Coil Conductor FDR 5/17/05 1 Michael Kalish NCSX TF Conductor.
NCSX Stellarator Core Pre-conceptual Design Progress and Status Mike Cole, Paul Goranson, Brad Nelson, Dave Williamson NCSX PAC Meeting PPPL June 3-4,
A PROPOSED TF JOINT DESIGN FOR THE NSTX CENTERSTACK UPGRADE Robert D Woolley 25 February 2009.
Stellarator Core Machine Configuration NCSX Project Meeting Dec 19-20, 2000 B. Nelson, M. Cole, P. Fogarty P. Goranson, G. Jones, D. Williamson O AK R.
Review of Modular Coil Winding Pack Configuration David Williamson March 19, 2004.
Update on PANDA solenoid design and analysis Gabriella Rolando Helder Pais Da Silva Herman ten Kate Alexey Dudarev 3 November
16 T dipole in common coil configuration: mechanical design
Instrumentation for status monitoring of SST-1 superconducting magnets
MANUFACTURING OF MAGNETS FOR SST-1 TOKAMAK
Full-scale trial results to qualify optimized manufacturing plan for ITER Toroidal Field coil winding pack in Japan Dummy double-pancake (DP) winding was.
Development of a low material endplate for LP1 and ILD
The CMS magnet superconducting coil
X.R. Wang, M. S. Tillack, S. Malang, F. Najmabadi and the ARIES Team
Status of Detector Solenoid and Anti-DID
FRESCA2 Update on the dipole design and new calculations
EuroCirCol: 16T dipole based on common coils
the MDP High Field Dipole Demonstrator
DCLL Blanket Analysis and Power Core Layout for ARIES-DB
Magnet Options Forward dipoles vs. forward solenoids
MQXF coil cross-section status
Elements of the TF coils that I visited:
Cross-section of the 150 mm aperture case
Proposed FNSF Quench Studies and Structural Studies Using MIT Twisted Stacked Tape HTS Superconductors P. Titus, February
Presentation transcript:

ARIES AT Project Meeting - Princeton, NJ 18 Sept 00 1 ARIES-AT Toroidal Field (TF) and Poloidal Field (PF) Coils Tom Brown, Fred Dahlgren, Phil Heitzenroeder (PPPL) September 18, 2000

ARIES AT Project Meeting - Princeton, NJ 18 Sept 00 2 ARIES AT TF and PF Design The ARIES AT TF and PF systems are based on YBCO high temperature SC. The coil configuration permits full replacement of the blanket/shield modules. Design is based on Ron Miller’s strawman ver. 306 & Chuck Kessel’s optimized PF system.

ARIES AT Project Meeting - Princeton, NJ 18 Sept 00 3 ARIES-AT Configuration Features High T SC TF No structure between TF outer legs: Permits blanket/shield/ divertor module removal.

ARIES AT Project Meeting - Princeton, NJ 18 Sept 00 4 Mechanical Arrangement Double Pan. TF Winding VV Blanket/Shield/PFC Module TF case PF coils Solenoid

ARIES AT Project Meeting - Princeton, NJ 18 Sept cm inner case added to TF structure TF Inboard/Outboard Case Detail Case structure built up to increase out-of plane stiffness

ARIES AT Project Meeting - Princeton, NJ 18 Sept cm inner shell added to TF inboard leg VV inner radii set at 2.83 m per strawman (ver 306) Details of the VV, blanket/shield and div module has not been updated in the TF Pro/E models Inboard Radial Build

ARIES AT Project Meeting - Princeton, NJ 18 Sept 00 7 Configuration Details

ARIES AT Project Meeting - Princeton, NJ 18 Sept 00 8 TF System 16 coils B 0 =5.9 0 =5.20 m 9.6 Mat / coil 2400 T/coil; double pancakes Wedged support YBCO Hi T on Inconel strip B S/C=11.1 T Wound construction –Permits grading; easier fabrication; better field orientation for higher J Stiffening ribs Intercoil Structure

ARIES AT Project Meeting - Princeton, NJ 18 Sept 00 9 TF Coil Case & Lead Details One coil case (shown) is configured for power leads. The other 15 coils are configured for coil to coil connections. Leads

ARIES AT Project Meeting - Princeton, NJ 18 Sept TF Coil to Coil Bus Connections Input lead details Coil-coil connection details

ARIES AT Project Meeting - Princeton, NJ 18 Sept Exploded View of Case Assembly Total Weight of a Single TF coil is 64 metric tons

ARIES AT Project Meeting - Princeton, NJ 18 Sept TF Coil Winding Double pancakes will be wound into the coil case channel via two spools which are sized to limit conductor strain to <0.2%.

ARIES AT Project Meeting - Princeton, NJ 18 Sept TF Superconductor 2 pancakes per coil; 20 turns per pancake Each turn has 20 x 3 “sub turns” for a total of 2400 turns/coil. I / sub turn = 9600 kAt/2400 t = 4 kA J sc =100 kA/sq. cm (10 micron thick film layer assumed). Strain limit 0.2%. Superconductor is conduction cooled by case; case is cooled by LN2. Inconel strip YBCO Superconductor Strip Packs (20 layers each) 8.5 mm CeO 2 + YSZ insulating coating (on slot & between YBCO layers) 430 mm

ARIES AT Project Meeting - Princeton, NJ 18 Sept Total Field at TF Conductor

ARIES AT Project Meeting - Princeton, NJ 18 Sept Radial Field at TF Conductor Worst Case field perpendicular to SC in Inner leg : B max ~ B T =11.1T

ARIES AT Project Meeting - Princeton, NJ 18 Sept Vertical Field at TF Conductor Worst Case Field perpendicular to sc in horizontal leg region: ~B max ~5.4 J T =100kA/sq.cm

ARIES AT Project Meeting - Princeton, NJ 18 Sept Conductor Operating Point Max. B-perp. For TF at 75K ~3.8 T Bmax., TF Bromberg and Tekula, “Options for the Use of High Temperature Superconductor in Tokamak Fusion Reactor Design” J allow., TF =100 kA/sq. cm Max. B-perp. For PF at 75K ~6 T

ARIES AT Project Meeting - Princeton, NJ 18 Sept TF Load Patterns Out of Plane In Plane

ARIES AT Project Meeting - Princeton, NJ 18 Sept Nastran TF Coil/Case Model (reinforced) Added inner Case Wall (100mm) Increased Outer Case Radial Depth (950mm) Increased Case Wall Thickness (160mm)

ARIES AT Project Meeting - Princeton, NJ 18 Sept Vertical TF Displacements due to Combined Loading (preliminary model)

ARIES AT Project Meeting - Princeton, NJ 18 Sept TF Displacements due to Combined Loading

ARIES AT Project Meeting - Princeton, NJ 18 Sept Coil Strain Due to Combined Loading (maximum principal - preliminary model) Max.Pr..Strain 7.7%

ARIES AT Project Meeting - Princeton, NJ 18 Sept Coil Strain due to Combined Loading (MaxPrinc.) w/Reinforced Case

ARIES AT Project Meeting - Princeton, NJ 18 Sept In Plane + Out of Plane Max. Pr. Stress

ARIES AT Project Meeting - Princeton, NJ 18 Sept In Plane + Out of Plane Tresca Stress On the Case -w/Reinforced Case.

ARIES AT Project Meeting - Princeton, NJ 18 Sept Poloidal Field System OH

ARIES AT Project Meeting - Princeton, NJ 18 Sept Poloidal Field Coil Design Uses YBCO / Inconel conductor similar to the TF. J =55 kA / sq. cm Gl-Polyimide Electrical Insulation Inconel strip “N” subturns of YBCO superconducting strip per slot. N varies with coil I requirements LN2 chill plates (option: pool boiling design)

ARIES AT Project Meeting - Princeton, NJ 18 Sept PF - Radial Fields Peak Radial Field 9.0 T Need to re-orient the conductor plane to horizontal. Peak Vertical Field is 8.7 T for PF-14 and 6.9 the conductor. We will need to reduce the current Density in PF-14. Peak Radial Field is only 7.7 T for PF 12 & 13 and 5.9 the conductor.

ARIES AT Project Meeting - Princeton, NJ 18 Sept PF - Vertical Fields Peak Vertical Field 9.3 T Peak Radial Field is only 7.7 T for PF 12 & 13 and 5.9 the conductor. PF-12 PF-13 PF-14

ARIES AT Project Meeting - Princeton, NJ 18 Sept Alternate PF Coil Orientation The maximum PF-14 normal field component will be 7 = 30kA/sq.cm

ARIES AT Project Meeting - Princeton, NJ 18 Sept PF Coil Supports & Stresses Stresses are OK:  allowable is ~600 MPa. based on 0.2% strain limit of SC, We still have to update drawings to coil & support dimensions used in analyses.