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Overview of LLCB TBM for ITER Paritosh Chaudhuri Institute for Plasma Research Gandhinagar, INDIA CBBI-16, 8 - 10 Sept. 2011, Portland , USA. Intruduction.
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Overview of LLCB TBM for ITER Paritosh Chaudhuri Institute for Plasma Research Gandhinagar, INDIA CBBI-16, 8- 10 Sept. 2011, Portland, USA
Intruduction In India, development of Lead-Lithium Ceramic Breeder (LLCB) blanket is being performed as the primary candidate of Test Blanket Module (TBM) towards DEMO reactor. The LLCB TBM will be tested from the first phase of ITER operation (H-H phase) in one-half of a ITER port no-2. The Indian TBM R&D program is focused on the development and characterization of materials: structural (IN-RAFMS), breeding materials (Pb–Li, Li2TiO3) and development of technologies for Lead-Lithium Systems, Helium Cooling Systems, Tritium Extraction Systems, TBM manufacturing and coatings.
Indian TBM Program India is developing Lead-Lithium cooled Ceramic Breeder (LLCB) TBM for testing in ITER Port No-2 with position of TBM Leader. • Lead-Lithium cooled Ceramic Breeder (LLCB) • Tritium Breeder: Lithium Titanate; • Coolant: Pb-Li eutectic alloy (multiplier and breeder) • FW coolant: Helium Gas; • Structural Material : Reduced Activation FMS • Helium purge gas for T extraction from CB
Input parameters for LLCB TBM neutronic calculations • Fusion Power : 500 MW, Neutron Wall load : 0.78 MW/m^2 • Pulse duration is 400 sec with pulse repetition time 1800 sec • Major and Minor radius of plasma: 6.3/ 2.1 m • Structural Material: IN-RAFMS (Eurofer as a reference material) • Shield Material:- SS-316 (65%) and water (35%) • Vacuum Vessel: Borated SS-316 cooled with water • Blanket materials: • -Pb-Li Eutectic (90 % Li-6) (Breeder, Multiplier and coolant) • -Li2TiO3 (60 % Li-6, Packing fraction 60%)(Breeder Material) • -He (Coolant for the First wall)
LLCB TBM in ITER sector model • A 15 degree sector of the ITER machine has been constructed. The shield and vacuum vessel has been made using the intersection of concentric tori and concentric cylinders. • TBM dimensions are taken as 1.66 x0.484x0.518 m^3 (pol x tor x rad ). TBM geometry has been modeled using the parallel planes. • A 20 cm thick water jacket has been placed around the TBM. 100 cm thick shield plug has been put after the TBM. Poloidal Radial view of ITER neutronic model (with LLCB TBM)
Power density profile & Total Power Deposition in LLCB TBM Total Power deposited in LLCB TBM is 0.62 MW
Preliminary LLCB TBM shield block design LLCB TBM + Shield Block in Frame assembly Schematic LLCB TBM Frame Assembly • The TBM in ITER will attenuate the flux ~1 order magnitude • To reduce dose rates this flux should be further reduced (~106 n/cm2 /s) for safety and maintenance purpose • The shield block consists of 60 % SS 316 LN and 40 % water (DM) Reference Solid TBM Sub-modules Shield block Shield Flange with lip seal
Thermal Hydraulics of ITER TBM • Main Objectives: • To optimize a suitable design of FW cooling w.r.t. Neutron wall load and heat flux. • To estimate the temperature and thermal stresses of all materials used in the blanket module and ensure these values are within design limits. • To keep the temperatures of ceramic breeder zones within the temperature window for effective Tritium release • To optimize the flow parameters (velocity, pressure)
LLCB First Wall Structure 480 568 20X11 20X20 R2.5 28 Circuit-1 Circuit-2 Total number of channels - 64 Number of circuits (counter flow) – 2 Number of passes per circuit – 4 Number of channels per passes – 8 Pitch: 25.5 mm (typical to all channels) Rib thickness between channels = 5.5 mm
Power Deposition on LLCB TBM Input Parameters - Total Heat Load: 0.616 MW - He inlet Temp: 300 C - He inlet pressure: 8 MPa - He velocity : 45 m/s - PbLi inlet Temp: 325 C - PbLi inlet pressure: 1.2 MPa - PbLi velocity: 0.1, - 0.5 m/s Assumptions - Flow is Steady and incompressible - Flow is turbulent Output: - Radial temp. profile in all zones; - PbLi velocity, Pressure Drop profile, outlet temp. Analytical Model
Radial Temperature Plot for LLCB TBM Temperature Distribution of LLCB TBM (for different V= 0.1, 0.2, 0.3, 0.5 m/s)
Radial temperature profile in different CB zones Radial temperature profile in different CB zones for PbLi velocity of 0.1 m/s
Peak Temperature at different zones in LLCB TBM Peak Temperature at different zones in TBM (for PbLi velocity = 0.1 m/s)
R&D Activities under progress (1/2) • Indian RAFMS Development: • Composition Achieved • Melts are under characterization (Microstructure & Mechanical properties) • Lead-Lithium Technologies development: • Lead-Lithium production • Pb-Li Corrosion experiments • Full scale Pb-Li loop development • Ceramic Pebbles Fabrication: • Lab scale pebbles (Lithium Titanate) • successfully fabricated • Pebble bed characteristics are under investigation • Large scale production plans are under progress
R&D Activities under progress (2/2) • Helium Loop development • ¼ the size loop development plan • Small scale TBM testing • Tritium Extraction Systems development • H/D extraction from Helium purge gas • H/D extraction from Pb-Li • Permeation Analysis
Work under Progress RAFM steel is a structural material under development for fusion reactor applications. Several fabrication processes for the production of TBM sub-components and assembly need to be investigated in the developmental program. For the fabrication of sub-components (first wall, stiffening plates, cooling plates and caps) using the Indian RAFMS different options are being considered to investigate its fabricability: HIP process, EB welding, Laser and Narrow Gap TIG welding.
Initial trials for First wall small scale mock-up by HIP process were carried out using stainless steel discs with pre-machined slots for making internal channels. Fig.6 shows the hipped part. EB welding on 6 mm thick austenitic stainless steel plates. Welds of this structure cleared both ultrasonic examination and radiography. Virtually no distortion was observed in this structure. It is planned to make similar structures using RAFM steel plates to gain experience in fabrication.
Alternative approach for FW fabrication Cutting of straight square channel by wire EDM followed by hot bending. advantage of this approach is that there will be no mating surface and therefore, no lack of bonding. However, challenges remain in cutting such a long square channel by wire EDM.
Summary • Institute for Plasma Research (IPR), collaboration with Bhaba Atomic Research Centre (BARC), Indira Gandhi Centre for Atomic Research (IGCAR) and other research institutions and universities within India involve the R&D activities focusing on ITER-TBM systems development . • The major areas of R&D activities are: • - Development of technologies of circulators, heat exchangers • and diagnostics for Lead-Lithium Systems, HCS, LL, TES • - Lead-Lithium Loop developments: • - MHD studies: • - Li2TiO3 Ceramic Pebbles development • The RpRs report on safety analysis have been submitted, • further detail work is in progress.
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MHD pressure drop in LLCB TBM The MHD pressure drop is calculated with an analytical expression for fully developed laminar flow in a rectangular duct. Channel Parameters Channel Height (2a) = 50 mm Channel Width (2b) = 484 mm Insulation layer (A2B2) thickness = 0.2 mm Outer wall (A1B1) thickness = 5 mm Channel length = 10 m Electrical conductivity : Pb-Li ~ 0.7e6, Fe wall ~1.4e6, Alumina ~ 1e-9 Hartmann number ~ 25000 Mean velocity is 0.1 m/s With Flow dividers • MHD Pressure Drop • Without coating : 122.5 kPa • With Alumina coating : 0.432 kPa Considerably small MHD pressure drop inside TBM
2D MHD Code: Velocity & induced field With alumina Without alumina Surface plot velocity profile More details in Poster NO: PO1-10, K.S. Goswami Velocity profile • Further work: • MHD effects in Manifolds & • in fringe field • Heat Transfer with MHD effects • Crack analysis contour plot of induced magnetic field
Analysis with 2-D MHD code Fully developed MHD flow in a rectangular channel Surrounded by various layers with different electrical properties Similar to S.Smolentsev et al. (FED, 2005) Velocity and induced magnetic field are calculated self consistently No-slip condition at the liquid-solid interface No induced magnetic field at the outer boundary of the computational domain
Validation of 2-D MHD code Comparison with analytical results