• DocumentCode
    3460726
  • Title

    Flow Optimization Studies for the ITER Shield Modules

  • Author

    Natoni, G.O. ; Youchison, D.L. ; Ulrickson, M.A. ; Sawan, M.E.

  • Author_Institution
    Sandia Nat. Lab., Albuquerque
  • fYear
    2007
  • fDate
    17-21 June 2007
  • Firstpage
    1
  • Lastpage
    4
  • Abstract
    A 3-d, 4-channel prototypical model representing a subset of an ITER neutron shield module was analyzed using computational fluid dynamics. We used this model to optimize the radial gaps in the coaxial flow drivers along with the depth of the radial holes or channels in the stainless steel modules. In addition to redirecting the flow first to the back of the module and then to the front, the flow drivers increase the pressure drop in the radial tubes to allow for more uniform flow distribution from the back-drilled manifolds. They also increase the fluid velocity near the wall for improved heat transfer. We sized the flow drivers to allow for 2, 3 and 4-millimeter (mm) gaps along the annuli. The depths of the radial channels below the manifold were 10, 15, 20, 25, and 30 mm for each of the 2, 3, and 4 mm radial gaps. The objective of the study was to ascertain if a fixed 90-mm length on the bottom flow driver could be utilized for radial channels of varying depth below the back-drilled manifold and still provide adequate cooling for the neutron thermal load. Our group also performed an optimization of the gap around the tee-vane in the shield module front header. Tee-vane gaps of 1, 2 and 3 mm were studied to assess the flow bypass and wall velocities at the end of the model. In this article, we present the results of a full matrix of flow simulations using the CFdesign CFD package. The study indicates that a 90-mm-long flow driver with a 4-mm radial gap can keep the steel around the radial tubes sufficiently cool up to 30 mm beneath the back-drilled manifold. We also discovered that flow bypass through the end gap on the tee-vane is relatively small and has little effect on cooling of the front cover plate for gap sizes as large as 3 mm.
  • Keywords
    channel flow; computational fluid dynamics; flow simulation; fusion reactor design; fusion reactor materials; fusion reactor theory; stainless steel; 3-d, 4-channel prototypical model; CFdesign; FeCrCJk; ITER neutron shield module; back-drilled manifolds; coaxial flow drivers; computational fluid dynamics; flow bypass; flow optimization; flow simulations; fluid velocity; heat transfer; neutron thermal load; pressure drop; radial channels; radial gaps; size 90 mm; stainless steel modules; tee-vane gaps; wall velocities; Coaxial components; Computational fluid dynamics; Cooling; Heat transfer; Neutrons; Packaging; Prototypes; Steel; Thermal loading; Transmission line matrix methods;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering, 2007. SOFE 2007. 2007 IEEE 22nd Symposium on
  • Conference_Location
    Albuquerque, NM
  • Print_ISBN
    978-1-4244-1193-1
  • Electronic_ISBN
    978-1-4244-1194-8
  • Type

    conf

  • DOI
    10.1109/FUSION.2007.4337896
  • Filename
    4337896