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AT Pilot Plant EM and Structural Studies

AT Pilot Plant EM and Structural Studies. P. Titus. Goals of the PPPL AT Pilot Plant EM and Structural Studies Basic Sizing and Stress Analysis of the TF Case and Winding Pack Including OOP

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AT Pilot Plant EM and Structural Studies

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  1. AT Pilot Plant EM and Structural Studies P. Titus

  2. Goals of the PPPL AT Pilot Plant EM and Structural Studies Basic Sizing and Stress Analysis of the TF Case and Winding Pack Including OOP Show Non-Constant Tension D is Acceptable – Provides more Effective PF Usage. Reduces Mass of the Machine, Increases Peak Field Study Inner Leg Winding Pack Cross Sections and Jacket Shapes Rectangular vs. Circular, Radial Plates, Extruded Square Conductor Study Inner TF Support Concepts Wedged Only Bucked Bucked and Wedged Heat Balance Re-Position the Joints to the Bore? – Saves Radial Build Disruption Simulations of Tom’s in-Vessel Structures

  3. AT Pilot Plant TF Structural Analysis Geometry and Currents Maxwell /Ansys Analyses by A. Zolfaghari • 30-degree slice modeled with one TF coil • TF current= 10MA per leg • PF &OH Currents from TSC code:

  4. EM Analysis B Fields 13.97T Body Forces on TF

  5. Structural Analysis

  6. Toms AT Structural Analysis Casing & Inter-coil Structure Stress Winding Pack Stress

  7. AT pilot plant device core (AT PILOT PLANT DEVICE CORE) (Tom Browns’s 2012 Vertical/Servicing Access Concept) Model With Symmetry Expansion Case Bending Stress Resulting from Deviation from Constant Tension D, Allowing PF Coils to be Closer to the Plasma Ali’s Model has Heavier Case Structures that Resist Bending

  8. Equivalent Stress with ITER TF Winding Pack Orthotropic Properties Wedging and Nose Compression Plus Vertical Tension

  9. Max Principal Stress with ITER TF Winding Pack Orthotropic Properties Mostly Vertical Tension From Vertical Separating Force

  10. Equivalent Stress in the Inner TF Leg Nose Stress with ITER TF Orthotropic Properties ITER grade inner TF casing SS 316 primary membrane stress allowable ITER TF Orthotropic Properties Table 2.2.3-1 ITER TF Orthotropic smeared Material Properties of the TF Coil WindingPack Used in 3D Global Non-linear ModelEx 61.7 GPa NUxy 0.237Ey 101. GPa NUyz 0.241Ez 49.4 GPa NUzx 0.161Gxy 27.7 GPa ax (for 293K to 4K) 0.304%Gyz 22.8 GPa ay (for 293K to 4K) 0.299%Gxz 6.68 GPa az (for 293K to 4K) 0.319%1) x = radial direction, y= poloidal (winding) direction , z = toroidal direction2) In the finite element code used Poisson’s ratio may be input in either major (PRxy, PRyz, PRxz) minor (NUxy, NUyz, NUxz) form Static Membrane Allowable = 2/3*1000MPa = 660 MPa LOW CYCLE OR NO FATIGUE

  11. Inner Leg TF Support Structures ITER Wedged Only with Radial Plates PPPL AT PILOT Rectangular Bent Tube Conductor Bucked (JET, ITER-Rebut), Poloidal Plates Other Possibilites: Bucked and Wedged Square Extruded Conductors

  12. Ansys Analyses by P. Titus Fields 2D 11.3T 3D 13.89 T Volumes 1 cm slice Mat 1 Jackets 1.318 e-3 m^3 Mat 2 Superconductor 1.442e-3 m^3 Mat 5 Insulation 6.259e-4 m^3 Mat 10 Case 1.798e-3 m^3 Winding Pack 3.386e-3 Total 5.183 e-3 m^3 Winding Pack Metal Fraction = 39% With no Vertical Tension (yet) Forces

  13. Tresca – With no Vertical Tension (yet)

  14. Hoop Stress

  15. Add ~390 Mpa Vertical Tension, Total is ~700 MPa Note that a Big Contribution to the Inner Leg Stress is the Vertical Separating Force, Which is Driven by External Structures and Where you Put the TF Outer Leg

  16. FIRE Simulation Model Using the External Structures Limit Analysis to Allow Other than Membrane Stress Allowable Use Rings to keep Corner Closed – And “Pinch” Inner Leg and Off Load Vertical Tension

  17. Beginnings of the AT Pilot Plant Disruption Model NSTX Disruption Model

  18. Current Densities in the Whole Model NSTX Including the TF

  19. Transient Thermal Analyses of the Tokamak Internal Components MIT Hot Divertor Collaboration (By H. Zhang, P.Titus) NSTX Global Heat Balance Calculations (By A. Brooks)

  20. We are Currently Analyzing ITER Joint Concepts for Outside the CS. If the AT has a low enough Bdot in the Bore – The Joints may be able to be located in the Bore. A. Brooks is Qualifying .22T/sec Radial Bdot for ITER ITER CS Coax Joint Model • 16 mm OD Superconducting Cable Modeled as petal and sub-petal with pitches of .45m and .25m • SC space filled with conductive material (hole not modeled) • 1mm Braze layer • 1mm SC lacing layer with pitch same as petal pitch .45m • 6mm Outer Shell • Joint 0.25m long • Unit resistivity (1nOhm-m) used for all transverse conduction ITER CS Twin Box Joint Model • Same 16 mm OD Superconducting Cable Modeled as petal and sub-petal with pitches of .45m and .25m • SC space filled with conductive material (hole not modeled) • Sole Plate 50mm wide, 30mm thick, .45m long (1 pitch length) • Cables 31mm center to center • Unit resistivity (1nOhm-m) used for all transverse conduction Pilot Plant CS Fields. Peak = 9.7T

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