Tritium building. Port cell. Hot cell. Ancillary systems TBM

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1 Hot cell Port cell Tritium building US DCLL TBM Ancillary systems TBM Reported by: Arnie Lumsdaine M. Abdou, M. Dagher, A. Ying, N.B. Morley, S. Smolentsev, S. Sharafat, A. Aoyama, M. Youssef UCLA C. Wong, M. Schaffer GA B. Merrill, L. Cadwallader INL R. Kurtz PNNL M. Sawan, E. Marriott UW Y. Katoh, A. Lumsdaine ORNL S. Willms LANL M. Ulrickson SNL Also monitored by: M. Hechler - ORNL He loops /rs 1

2 Thermomechanical Modeling of Blanket Systems Presenting: Arnold Lumsdaine ORNL Joseph Tipton University of Evansville Shahram Sharafat, Aaron Aoyama, Mo Dagher UCLA Ed Marriott, Mohamed Sawan University of Wisconsin, Madison Clement Wong, General Atomics Mike Ulrickson, Sandia National Lab Fusion Nuclear Science and Technology Annual Meeting August 2, 2010

3 TBM Nuclear Heating Values Nuclear heating values for each steel component were obtained. Detailed 3D nuclear heating results from DAG-MCNP calculations were used to obtain per-component values. Locations of Planes where data were obtained Total nuclear heating in FS components were determined from the CAD-based 3D calculations to be MW. The per-component heating values can now be used in the full analytical analysis of the helium circuit within the TBM. 3D Nuclear Heating Results on Planes Y2 (left) and X1 (right) 3 Managed by UT-Battelle

4 TBM Nuclear Heating Values Average nuclear heating data per Volume Component (cm 3 ) component were obtained from the detailed nuclear heating profiles. Top Plate Nuclear Heating [kw] Bottom plate Based on the volume per component, the total NH per component was calculated. Those totals add up to the total FS nuclear heating of MW determined from the 3D analysis. Grid Plates Dividers & Plenum First Wall (Front) First Wall (Sides) Inner He Manifold Outer He Manifold LL Horizontal Plate Total Nuclear Heating in FS Managed by UT-Battelle

5 Helium Circuit Analytical Analysis Using the new nuclear heating values it is now possible to rework an analytical solution for the first helium circuit. This includes: Optimizing the variation in the number of channels per first wall pass Calculating the pressure drop in the TBM Determining i the correct flow parameters for the helium HELIUM PROPERTIES Density 6.1 kg/m 3 Specific Heat 5200 J/kg-K Thermal Conductivity W/m-K Viscosity 3.50E-05 kg/m-s ENVIRONMENTAL PARAMETERS Heat Flux Max 0.5 MW/m 2 Neutron Wall Loading 0.78 MW/m 2 First Wall Nuclear Heating 7.07 MW/m 3 Total First Wall Q (Flux) MW Total Nuclear Heating MW Q - TBM (total) MW TBM FLOW REQUIREMENTS Analysis will be performed for the worst case scenario, at high performance and low flow rate, while maintaining the FS Tmax < 550 C C. Inlet Temperature e -T in 350 C Outlet Temperature - T out 410 C T 60 C Required Mass Flow Rate kg/s Required Volume Flow Rate m 3 /s 5 Managed by UT-Battelle

6 ANSYS CFX Validation: Channel Flow Turbulent Heated Pipe Flow Pressure Drop [Pa] Empirical CFX Smooth 69,486 69,320 Rough 252, ,938 Outlet Heat Transfer Coefficient h x (L) [W/m2-K] Empirical CFX Smooth 15,395 +/- 10% 14,996 Rough 34,810 +/- 5% 36,508 Turbulent Heated Square Duct Flow 6 Managed by UT-Battelle

7 ANSYS CFX Validation: Square Channel w/ One Side Rib Roughened GOAL: Find equivalent sand grain roughness height (k s ) to model rib roughening in ANSYS CFX CASE 1: Fluid Flow Validation Youn et al., J Fluid Eng, 116 (1994) Friction predicted reasonably well at low rib heights CASE 2: Heat Transfer Validation Hirota et al., J Heat Transf, 116 (1994) Wall ribs over-influence flow and under-influence temperature profiles Heat transfer under-predicted di d by 25% Temp Non-D Cross-Section 7 Managed by UT-Battelle

8 TBM DCLL Representative He Channel m 0. 1kg s Fluid Flow: He Gas Heat Transfer: He Gas, Ferritic Steel Solid BCs: m 0. 1kg Tin 350 o C s ε 0. 4 mm q W m Symmetry Insulation Radial Distribution of Power Density Mid-plane zone (1275 mm height) Neutron Wall Loading = 0.78 MW/m 2 (Sawan, TBM, Aug08) 8 Managed by UT-Battelle

9 TBM DCLL Representative He Channel Results: Recirculating flow present in channel ends, past inlet, and in outlet P = 20,130 Pa Maximum solid temperature likely too high due to insulating boundary conditions T AVG,OUT = 637 K T AVG = 14 K 9 Managed by UT-Battelle

10 Conclusions and Future Work CONCLUSIONS: Smooth wall flow and heat transfer validated for various geometric channels Effects of sand grain roughness have been validated Correlating rib roughening with an equivalent sand grain roughness in ANSYS CFX is not effective for most realistic cases FUTURE WORK: Develop effective rib roughening model for both flow/temperature in ANSYS CFX Complete solution of one-sided roughened surface with a design that includes manufacturability considerations Model flow through one He multi-channel pass of DCLL TBM Flow distribution optimization through manifold of DCLL TBM Coupled structural thermal/fluid model of He channels with Ferritic Steel first wall structure 10 Managed by UT-Battelle