Overview of UCLA Research Activities on Fusion Nuclear Science and Technology

1. Overview of UCLA Research Activities on Fusion Nuclear Science and Technology Briefing to Professor Osamu Motojima and Japanese delegation from NIFS and MEXT Signing Ceremony for Agreement on Scientific Exchange and Cooperation between Japan (NIFS) and UCLA (HSSEAS and CESTAR) Mohamed Abdou November 28, 2006

2. UCLA Activities in Fusion Nuclear Science and Technology • US ITER Test Blanket Module Activity: • Technical Planning, Design, and Analysis • Modeling Development and Experimental Activities • JUPITER-II (started April 2001) • Molten Salt Thermofluid MHD Flow Simulation • Solid Breeder/SiC Material System Thermomechanics • Solid breeder blanket research activates under IEA Collaboration • Tritium permeation and control • Interface thermal conductance • ITER Basic Machine and US Procurement Package Support • Free Surface Liquid Metal MHD Experiments and Modeling for Liquid Divertors and Melt Layers • Z-pinch Vapor Recombination Dynamics Study

3. A proposed technical plan for US ITER TBM has been developed over the past 1.5 years. An external review of US DOE technical and project experts found the cost and plan “complete and credible” and “ready to be implemented” The cost averages between $5M to $10M per year over the next 10 yrs for all the R&D, Design, Fabrication and Testing needed for the US H-H Phase TBMs and supporting systems. The exact amount depends on the level of international collaboration and degree of integration among ITER Parties A significant fraction of the manpower, facilities, codes and other important resources already exist in the base program US ITER TBM UCLA Leadership in the Development of the US TBM Technical Plan and Cost Estimate

4. US ITER TBM UCLA Plays a Lead Role on US-TBM DCLL TBM Module (1660 x 484 x 410 mm) • UCLA Roles: • US solid breeder TBM scaling, test module design • US DCLL thermofluid MHD experiments and simulations • US TBWG representation Poloidal flow PbLi Channel He-cooled RAFS FW SiC FCI Proposed US baseline strategy proposes different levels of participation for two US TBM concepts – official US program under consideration at DOE HCCB TBM sub-module (710  389  510 mm) Ceramic breeder pebbles He-cooled RAFS FW Be Pebbles

5. US ITER TBM HCCB Joint Partnership Preliminary discussions occurred among US, Japan, and Korea about a possible partnership on HCCB. KO Submodule JA Submodule The proposed US HCCB sub-module will occupy 1/3 of an ITER horizontal half-port US Submodule The back plate coolant supply and collection manifold assembly, incorporating various penetration pipes, flexible supports, and keyways, should be collaboratively designed by partner Parties.

6. B-field He FCI PbLi UCLA MHD group is one of the world’s key teams working in the area of fusion LM MHD • Blanket performance is strongly affected by MHD phenomena • UCLA group performs MHD studies under DCLL blanket conditions for both DEMO blanket and ITER TBM. • Strategy encompasses: • Full 3D simulation tool development • Models for specific phenomena (e.g. natural convection, MHD turbulence) • Key EXPERIMENTS to validate/improve simulations and understanding DCLL DEMO BLANKET Flow Channel Insert is the key element of the DCLL concept, serving as electric and thermal insulator

7. UCLA is collaborating on HIMAG 3D - a complex geometry simulation code for Closed and Open Channel MHD flows • Simulations are crucial to both understanding phenomena and exploring possible flow options for DCLL and FCIs, and NSTX Li module • Problem is challenging from a number of physics and computational aspects requiring clever formulation and numerical implementation • Consistent and conservative scheme developed to conduct the simulation of MHD with high accuracy at high Hartmann numbers Pipe flow on unstructured grid in strong field gradient – good match to experimental data at high Ha Bmax = 2.08 T, Ha = 6640 N = 11061, Re = 3986 U = 0.07 m/s

8. E D B A C g DEMO Model development focuses on key MHD phenomena that affect thermal performance via modification of the MHD velocity field • Formation of high-velocity near-wall jets B.2-D MHD turbulence in flows with M-type velocity profile C. Reduction of turbulence via Joule dissipation D. Natural/mixed convection changes flow field dramatically E. Strong effects of MHD flows and FCI properties on heat transfer =5 =100 =500

9. US ITER TBM The ferritic structural box with the first wall helium coolant channels for the HCCB TBM. (CAD model from SolidWorks) CAD Model Input Fix CAD model CAD to Analysis Intermediaries Neutronics Electromagnetics Temperature field from Thermo-Fluid Analysis using SC/Tetra Thermo Fluid Deformation (Thermal expansion) field from structural analysis using ANSYS Structural Mass Transfer VTBM - Integrated Data/multi-code multi-physics modeling activities, or Virtual TBM, is key for ITER TBM R&D activity. • The design of a complex system like the ITER TBM requires an exhaustive CAE effort encompassing multiple simulation codes supporting multi-physics modeling.

10. UCLA Facilities and Capabilities Utilized in JUPITER-II Collaboration on Flibe Thermofluid MHD Research with Japanese Universities UCLA MTOR MHD Facility Test section lit by pulsed YAG laser during Particle Image Velocimetry measurements BOB magnet JUPITER 2 MHD Heat Transfer Exp. in UCLA FLIHY Electrolyte Loop

11. JUPITER-II Key Result - Strong MHD effect on turbulenceseen, even at low Ha typical of low conductivity Flibe velocity fluctuations severely reduced… Near wall temperature increases… Ha = 0 and global Nu number decreases… Ha = 20 Re = 5400

12. A constant force of 4 N is applied to each bolt during the course of the experiment. CEA Li2TiO3 pebbles/ CVD SiC clad with Keyence High Precision Laser position system for displacement measurement Kovar Capacitance displacement sensor SiC plate Li4SiO4/Li2O pebble bed SS-316 Port available for laser displacement sensors JUPITER-II SiCf/SiC Breeder Pebble Bed Thermomechanics Interaction Study Deformation/Stress/Creep Datawere used in conjunction with UCLA DEM simulation code to develop temperature dependent stress/strain constitutive correlations – vital for accurate finite element analysis

13. Divertor design for NSTX UCLA Research on Liquid Metal Free Surface MHD for Liquid Divertor: Modeling & Experiments • The use of fast flowing lithium films as divertor target will lead to considerable improvement in plasma performance by gettering of impurities, allowing low recycling operation and handling of the high heat loads. • A good understanding of the dynamics of fast flowing liquid metal streams under spatially varying three component magnetic fields has to be established. Experiments on film flows show turbulent fluctuations organize into 2D structures with vorticity along the magnetic field ‘Pinching in’ seen in HIMAG simulations and experiments Flow ‘Pinching in’ The free surface structure is affected by the magnetic field, thus influencing its transport properties governing the heat and mass transfer. Flow can ‘Pinch-IN’ in field gradients and separate from the wall. This phenomenon is observed in experiments and numerical modeling, creating undesireable ‘bare spots’

14. Conceptual Z-pinch power plant A novel double pulse spectroscopic diagnostic was developed at UCLA to evaluate the feasibility of separating the Z-Pinch RTL material from the molten flibe Double pulse spectroscopy 1st pulse (high energy) used to produce and excite/ionize Fe & salt vapor Initial results suggested that effective means of separating either metal halides or precipitated metal (after hydro-fluoridation) from liquid flibe will need to be investigated for Z-IFE. 2nd pulse (low energy) used to re-excite Fe, Na after a time delay of 140-300 s

15. UCLA Activities in Fusion Nuclear Science and Technology • US ITER Test Blanket Module Activity: • Technical Planning, Design, and Analysis • Modeling Development and Experimental Activities • JUPITER-II (started April 2001) • Molten Salt Thermofluid MHD Flow Simulation • Solid Breeder/SiC Material System Thermomechanics • Solid breeder blanket research activates under IEA Collaboration • Tritium permeation and control • Interface thermal conductance • ITER Basic Machine and US Procurement Package Support • Free Surface Liquid Metal MHD Experiments and Modeling for Liquid Divertors and Melt Layers • Z-pinch Vapor Recombination Dynamics Study