Experimental Facility to Study MHD effects at Very High Hartmann and Interaction parameters related to Indian Test Blanket Module for ITER P. Satyamurthy Bhabha Atomic Research Centre, India P. Satyamurthy, December 21-23, 2009, IITK
Team members P. Satyamurthy, P. K. Swain, D. Kumar, K. Kulkarni, S. Kumar, D. N. Badodkar and L. M. Gantayet Bhabha Atomic Research Centre, Mumbai-400085 E. Rajendra Kumar, R. Bhattacharyay and G. Vadolia Institute of Plasma Research, Gandhi Nagar, Ahmedabad- 382428 P. Satyamurthy, December 21-23, 2009, IITK
Fusion Energy Lecture Contents ITER (International Thermo-nuclear Experimental reactor) Indian TBM Experimental and Theoretical programme for development of Indian TBM P. Satyamurthy, December 21-23,2009, IITK
Origin of Nuclear Fusion Energy Deuterium 17.6 MeV Neutron 80% of energy release (14.1 MeV) Used to breed tritium and close the DT fuel cycle Li + n T + He Tritium Helium 20% of energy release (3.5 MeV) Illustration from DOE brochure Deuterium and tritium is the easiest, attainable at lower plasma temperature, because it has the largest reaction rate and high Q value and hence the program is focused on the D-T Cycle P. Satyamurthy, December 21-23, 2009, IITK Ref: Prof. Abdou, UCLA
Advantages of Fusion Energy Sustainable energy source No emission of Greenhouse or other polluting gases No risk of a severe accident No long-lived radioactive waste Fusion energy can be used to produce electricity, hydrogen and for desalination.
Technology Issues in Fusion Energy Requires High temperatures (Millions of degrees) in a pure High Vacuum environment are required Technically complex and high capital cost reactors are necessary Still in R&D Stage
Fuel Cycle for Fusion Energy Deuterium from water (0.02% of all hydrogen is deuterium) Tritium from lithium (a light metal common in the Earth s crust)
Tritium Breeding 6 Li (n,α) t Natural lithium: 7.42% 6 Li and 92.58% 7 Li Required: 90% 6 Li and 10% 7 Li 7 Li (n;n α) t P. Satyamurthy, December 21-23, 2009-ITK
Neutron Multipliers for Fusion Energy Growth Desired characteristics: Small absorption crosssections Large (n, 2n) crosssection with low threshold Candidates - Beryllium, Lead Candidates: Beryllium is the best (large n, 2n with low threshold, low absorption) 9 Be (n, 2n) Pb (n,2n) Pb is most effective in Li-Pb eutectic P. Satyamurthy December 21-23, 2009-IITK
ITER Objectives Demonstrate the scientific and technological feasibility of fusion energy Demonstrate extended burn of DT plasmas, with steady state as the ultimate goal Integrate and test all essential fusion power reactor technologies and components Demonstrate safety and environmental acceptability of fusion. P. Satyamurthy, December 21-23,2009-IITK
THE ITER DEVICE International Thermonuclear Experimental Reactor Parameters Total Fusion Power Q- Fusion Power /Auxiliary heating power 500 MW 10 Average Neutron wall loading 0.57 MW/m 2 Plasma Major Radius Plasma minor Radius Plasma Current Toroidal Field at major radius 6.2 m 2.0 m 15 MA 5.3 tesla Plasma Volume 837 m 3 Height: 25 m, Diameter: 28 m Neutrons Generated 1.5 x 10 20 n/s 11
Typical DEMO Reactor 12
Major Sub-systems of ITER Shield Blanket Vacuum vessel Radiation Plasma Neutrons First Wall Tritium breeding zone Coolant for energy conversion Magnets P. Satyamurthy, December 21-23, 2009- IITK
BLANKET Functions Tritium Breeding High grade heat extraction Radiation Shielding 14
ITER is a collaborative effort among Europe, Japan, US, Russia, China, South Korea, and India
ITER Location- Caradache (France)
Typical ITER-TBM (proposed by US) 3 ITER equatorial ports (1.75 x 2.2 m 2 ) for TBM testing Bio-shield He pipes to TCWS Each port can accommodate only 2 modules (i.e. 6 TBMs max) Typical TBM System 2.2 m A PbLi loop Transporter located in the Port Cell Area Vacuum Vessel TBM System ( Heat Extraction from Neutrons & First wall radiation + T Breeding) P. Satyamurthy, December 21-23,2009-IITK
Indian TBM System 18
Indian Lead-Lithium cooled Ceramic Breeder (LLCB) TBM First wall Top-bottom plate assembly Breeder assembly Inner back plate Outer back plate Manifolds and pipes Flexible housings and support keys Poloidal 1660 mm Toroidal 480 mm Radial 536 mm
Details of Indian TBM P. Satyamurthy, December 21-23, 2009- IITK
Flow Configuration Indian LLCB TBM
LLCB DEMO / TBM Design Parameters Dimensions Plasma Facing Material ~1.7(P) x 1.0 (T) x 0.5(R) m (DEMO) ~ 1.7(P) x 0.5(T) x 0.5(R) m (TBM) Be coating (~2 mm) Structural material RAFMS Breeder PbLi, Li 2 TiO 3 Neutron Wall Loading Total Power Deposition 2.42 MW/m 2 (0.78MW/m 2 ) 2.24 MW (0.857 MW) Average. Heat Flux 0.5 MW/m 2 Primary Coolant PbLi and Helium P. Satyamurthy, December 21-23, 2009-IITK
MHD Effects in TBM P. Satyamurthy, December 21-23, 2009, IITK
The Liquid Metal MHD in TBM Flow across the magnetic field induces current J in the fluid volume. This current interacts with the magnetic field to produce opposing Lorentz force (JxB o ) The current also produces induced magnetic field along x Due to All these effects: 1) Additional pressure drop 2) Flow modifications 2) Additional joule heating 3) Turbulent suppression or 4)Hartman effects can make the flow 2-D turbulent X- flow direction Y-Induced current Z- Applied Magnetic Field Walls perpendicular to B-Hartmann walls Walls parallel to B side walla
Equations Governing Flow in TBM 3-D MHD-CFD code is being developed 1) ANUPRAVAHA IIT-BARC Code (Prof. Eswaran,IITK) 2) M/s Fluidyne (Bangaluru)
Non-dimensional Parameters in MHD flow Interaction Parameter-Ratio of magnetic body force to inertial force Magnetic Reynolds number-ratio of induced magnetic field to applied field Hartmann Number Ratio of Magnetic body force to Viscous force This ratio decides the flow structure 3-D turbulence or 2-D turbulence or Laminar
Hartmann-effect Increasing Hartmann Number P. Satyamurthy, December 21-23,2009-IITK
MHD effects- M profiles Across Side walls σ s i d e = 0, σ HWall = σ s i d e =, σ HWall = u average = 0.036 m/s
Effect of transverse B variation - Transition to M- Profile (strong function of N) -Generation of additional currents P. Satyamurthy, December 21-23,2009-IITK
Effects of MHD on Turbulence Non uniform Suppression of Turbulence -2D turbulence Introduction of Turbulent Anisotropy This has a bearing on: Pressure drop in the module Heat Transfer
MHD Effects on Turbulence
2-D MHD Turbulence Ref: Smolentsev et al Vorticity Distribution-Ha/ Re>>1/300
Combined Forced & Natural Convection - Buoyancy Effects + Suitable Turbulent Model
Flow complexity in TBM Flow - U bend U y U x U y B z Toroidal Flow U y -Downwords Flow U y - Upwards Poloidal- y Toroidal-z Flow -L bend Radial-x U x U y L-bend Under Developed Flow - Transient Region U x, Geometry change
Experimental Programme to Study MHD Phenomena in TBM
Properties Similarities of Pb-Li, Hg and Pb-Bi liquid metals Pb-Li (300 0 C) Hg (50 0 C) Pb-Bi Density kg/m 3 9500 13352 10360 Electrical Conductivity mho/m 0.77x10 6 1.02x10 6 ~1.0x10 6 Viscosity m 2 /s 0.188x10-6 0.116x10-6.187x10-6 Thermal conductivity W/mK 13.2 9.67 12.7 Pr 0.0238 0.022 0.022 C p J/kg-K 190 139.5 146.5
TBM Mercury-TBM B ~4T ~2.0-1.8 T Ha ~18500 ~6000 Re ~ 50,000 ~24500 N ~ 6700 ~1200 Ha/Re ~0.36 ~0.22 B = 4T Pb 83%-Li -17% (enriched 90% of Li 6 ) T i = 380 0 C, v =0.1m/s Actual TBM Scale down Mercury TBM
Proposed Mercury facility for MHD studies (Ha ~6000, N ~2000, Re ~15,000) Coil Cooling tower water supply in. HX Pump Control Valve Flow meter Magnet~2 T Mercury- TBM BGV Dump Tank
Major components of the MHD-TBM Simulation Facility MHD-TBM Mercury 1.5 tons Magnet - ~2.0T electro magnet Dump Tank Heat Exchanger Mercury-Water Pump -Vertical Cantilever Centrifugal pump Embedded Heaters in the walls to simulate solid breeder heat Diagnostics Primary coolant circuit Water Thermal Insulation Control & Instrumentation Power supplies and Utilities Motor for magnet movement Safety related instrumentation
Simulation of Nuclear Heat and Solid Breeder Heat Generation in Mercury-TBM Heat deposition area of LLCB TBM (m 2 ) First wall 1.62 0.424 Top & Bottom wall 0.436 0.424 Right & Left wall 1.62 0.436 First Solid Breeder 1.4746 0.424 Second Solid breeder 1.4746 0.424 Third Solid Breeder 1.4746 0.424 Heat generation in LLCB TBM Walls (kw) Surface heat flux (kw/m 2 ) Heat to be supplied in Mercury TBM for heat flux simulation (kw) 59 ~ 43 ~ 6.9 33.6 7.0 ~ 2.8 (for each wall) 66.8 23.64 ~ 5.1 (for each wall) 42.2 33.75 ~ 9.0 31.3 25.0 ~ 6.7 18.4 14.71 ~ 2.0
Diagnostics in the Mercury-TBM Ports: Thermocouple in Hg (1) :58 no.s Thermocouple in wall (2) : 46 no.s Velocity Profile meter : 08 no.s Pressure :08 no.s Potential pins in Wall :181 no.s
Process details of the Facility
Current Status of the Facility Basic and Process design is complete Civil works are in progress Sizing and specifications of most of the components are completed Vendor for detailed mechanical design of the TBM has been finalised Instrument and diagnostic equipment procurement has started Expecting the facility to be ready by early 2011
Conclusions India is proposing an LLCB - TBM for ITER MHD effects dominate the thermal-hydraulics of TBM (Ha ~18500, N~6700, Ha/Re ~ 0.36) For Successful design of TBM many MHD issues are needed to be understood An Experimental facility based on Mercury is being setup to under stand and address these issues In addition MHD-CFD code suitable for TBM design is being developed
Thank You