US ITER TBM DCLL TBM Design Analysis and

US ITER TBM DCLL TBM Design, Analysis and Development C. Wong, M. Dagher, S. Smolentsev and S. Malang FNS/TBM Meeting UCLA, September 19 -20, 2007

Base-line DCLL design US ITER TBM Objectives: • A design that has minimum credibility issues, mainly on configuration and fabrication, with design flexibility and support from MHD analysis • A design should be suitable for the DEMO application • A design that is simple enough and the design team members feel comfortable with • A design approach that can aid IO’s goal of ancillary equipment standardization but not given up our DCLL design features and objectives • A design flexible enough to accommodate the look-a-like and act-a-like approaches via the use of sub-modules

US ITER TBM DCLL presented at TBWG-18

DCLL TBM Design Pb-Li Flow Channels US ITER TBM Pb. Li Outlet Flow Channel Pb. Li Outlet Manifold Pb. Li Inlet Flow Channel

Helium Flow Circuit FW He circuit 1 TBM He circuit From Seventh Pass To Top Plate FW pass 2 US ITER TBM He in FW pass 1 Seventh Pass Sixth Pass From Fifth Pass Fourth Pass From Fourth Pass Top Plate From Third Pass Second Pass From 1 st Pass Third Pass Grid Plates Divider Plates From Second Pass He in START: Into 1 st Pass (Includes Bottom Plate) Back Plate He out Bottom Plate

Top Plate He Flow Channels Flow path: circuit 1, pass 7, channels 1 -3 (of 4 total) Flow path: circuit 1, pass 7, channel 4 (of 4 total) Flow path: circuit 2, pass 7, channels 1 -4 (of 4 total) He Flow Into Grid Plate I am very un-easy with this top plate design and fabrication, which will have to handle all the He coolant and properly distribute the coolant through separation and grid plates. It will be more difficult for DEMO and it could create void space. US ITER TBM NOTICE THE COUNTERFLOW OF THE HELIUM CIRCUITS

Possible modifications for the base-line DCLL US ITER TBM 1. Review Pb. Li routing to minimize power loss to colder Helium streams, decoupled impact from FCI 2. To accommodate IO standardization direction change concentric Pb. Li pipes to two separate inlet and outlet pipes 3. Review helium routing scheme to the separation and grid plates 4. Intention of applying second backplate to accommodate act-a-like tests and sub-modules

Item 1. Pb. Li routing to minimize power loss to colder Helium streams, decoupling impacts from FCI US ITER TBM DEMO energy loss: 1 st estimate by Wong: With Q’’’ input and looked at T differences between channels: Case x: Front/middle/back channels Case 1: Up down… 531 Case 2: Down up up……. 319 DCLL DEMO Case 3: Up down Up……. 520 Case 4: Up up down……. 572 Case 5: Up down up……. 285 no leakage in zone 2 Case 2 seems to have lower leakage 2 nd estimate by Sergey’s modeling: In terms of heat leakage into He, the case 2: Down up up option has advantages over the Case 1: up down scheme. Recommendation: To assess the following in coordination with the FCI design 1. For TBM change the Pb. Li to back-up front-down configuration. 2. But to avoid counter flow at the front wall, go back-down and front up configuration. Implying re-location of the Pb. Li inlet outlet pipes to the top TBM Ref as of April 2007 Pb. Li In and out at bottom TBM Base-line Sept 2007 Pb. Li In and out at top FW He should still be moving from bottom to Top.

US ITER TBM Item 2. We may or may not evolve our design similar to the HCLL back plate design, but with separate inlet and outlet Pb. Li pipes design would be easier to adjust than the concentric pipes design for IO connection standardization. With the second back plate design we can test concentric pipes in future test modules. HCLL Back plate design

US ITER TBM Item 3: Should we consider radial flow in the radial plate, and use the separation plate as helium plenum?

HCLL TBM Design: Updated geometry US ITER TBM

US ITER TBM

US ITER TBM

US ITER TBM We will keep the first wall helium cooling configuration and Mo and Ed will assess the possibility of radial flow to cool the radial and separation plates similar to the EU HCLL approach

Item 4: Second back plate US ITER TBM There is room here to move the shield back to accommodate a scond back plate. First back plate 1 We could add second back plate to adjust to our specific tests for future modules.

US ITER TBM Possibility of adding a second back plate

US ITER TBM Possibility of adding a second back plate

Proposed Modifications for base-line DCLL TBM US ITER TBM 1. 2. 3. 4. Pb. Li flow back down front up with coordination with FCI design Replace concentric Pb. Li pipes with two inlet and outlet pipes Utilize radial flow in radial plates and use separation plate as plenum Consider the possibility of 2 nd back plate option to be implemented in the future* *The 2 nd back plate mostly likely will need to be fabricated from non-ferromagnetic material, and the amount of RAFM piping should also Be checked. We need to check the possible need of reducing the Pb. Li Tout<420 C when the compatibility of Pb. Li/SS becomes important. As the design evolves, design details should include improved FCI design, minimum impacts from Pb. Li reversed flow and meeting of material compatibility limits with minimum amount of RAFM steel