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
Lecture Contents • Fusion Energy • 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 Used to breed Deuterium 80% of energy 17.6 MeV Neutron tritium and close release the DT fuel cycle (14.1 MeV) Li + n → T + He Helium Tritium 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 Ref: Prof. Abdou, UCLA P. Satyamurthy, December 21-23, 2009, IITK
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. P. Satyamurthy, December 21-23, 2009-IITK
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 P. Satyamurthy, December 21-23, 2009-IITK
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) P. Satyamurthy, December 21-23, 2009-IITK
Tritium Breeding Natural lithium: 7.42% 6 Li and 92.58% 7 Li Required: 6 Li (n, α ) t 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 Candidates - Beryllium, Lead Desired characteristics: – Small absorption cross- sections – Large ( n , 2 n ) cross- section with low threshold • Candidates: – Beryllium is the best (large n , 2 n with low 9 Be (n, threshold, low 2n) Pb (n,2n) absorption) – 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 500 MW Q- Fusion Power /Auxiliary ≥ 10 heating power Average Neutron wall loading 0.57 MW/m 2 Plasma Major Radius 6.2 m Plasma minor Radius 2.0 m Plasma Current 15 MA Toroidal Field at major radius 5.3 tesla Plasma Volume 837 m 3 Neutrons Generated 1.5 x 10 20 n/s Height: 25 m, Diameter: 28 m 11 P. Satyamurthy, December 21-23, 2009-IITK
Typical DEMO Reactor 12 P. Satyamurthy, December 21-23, 2009-IITK
Major Sub-systems of ITER Shield Vacuum vessel Blanket Radiation Plasma Neutrons First Wall Coolant for energy Magnets conversion Tritium breeding zone P. Satyamurthy, December 21-23, 2009- IITK
BLANKET Functions Tritium Breeding High grade heat extraction Radiation Shielding P. Satyamurthy, December 21-23, 2009-IITK 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 ) He pipes to • 3 ITER equatorial TCWS Bio-shield ports (1.75 x 2.2 m 2 ) for TBM testing • Each port can accommodate only 2 modules (i.e. 6 TBMs max) A PbLi loop Transporter located in the Port Cell Area 2.2 m Typical TBM System Vacuum Vessel TBM System ( Heat Extraction from Neutrons & First wall radiation + T Breeding) P. Satyamurthy, December 21-23,2009-IITK
Indian TBM System 18 P. Satyamurthy, December 21-23, 2009-IITK
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 P. Satyamurthy, December 21-23, 2009-IITK
Details of Indian TBM P. Satyamurthy, December 21-23, 2009- IITK
Flow Configuration – Indian LLCB TBM P. Satyamurthy, December 21-23, 2009-IITK
LLCB DEMO / TBM Design Parameters Dimensions ~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) Plasma Facing Be coating (~2 mm) Material Structural material RAFMS Breeder PbLi, Li 2 TiO 3 Neutron Wall 2.42 MW/m 2 (0.78MW/m 2 ) Loading Total Power 2.24 MW (0.857 MW) Deposition 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 X- flow direction or Y-Induced current 4)Hartman effects can make the Z- Applied Magnetic Field flow 2-D turbulent Walls perpendicular to B-Hartmann walls Walls parallel to B – side walla P. Satyamurthy, December 21-23, 2009-IITK
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) P. Satyamurthy, December 21-23, 2009-IITK
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 P. Satyamurthy, December 21-23, 2009-IITK
Hartmann-effect Increasing Hartmann Number P. Satyamurthy, December 21-23,2009-IITK
MHD effects-‘M’ profiles Across Side walls σ s i d e = ∞ , σ s i d e = 0 , σ HWall = ∞ 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 P. Satyamurthy, December 21-23, 2009-IITK
MHD Effects on Turbulence P. Satyamurthy, December 21-23, 2009-IITK
2-D MHD Turbulence Ref: Smolentsev et al Vorticity Distribution-Ha/ Re>>1/300 P. Satyamurthy, December 21-23, 2009-IITK
Combined Forced & Natural Convection - Buoyancy Effects + Suitable Turbulent Model P. Satyamurthy, December 21-23, 2009-IITK
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 Radial-x Flow -L bend U x U y – L-bend Transient Region Under Developed Flow - U x , Geometry change P. Satyamurthy, December 21-23, 2009-IITK
Experimental Programme to Study MHD Phenomena in TBM P. Satyamurthy, December 21-23, 2009-IITK
Similarities of Pb-Li, Hg and Pb-Bi liquid metals Properties Pb-Li Hg Pb-Bi (300 0 C) (50 0 C) Density kg/m 3 9500 13352 10360 Electrical 0.77x10 6 1.02x10 6 ~1.0x10 6 Conductivity mho/m Viscosity m 2 /s 0.188x10 -6 0.116x10 -6 .187x10 -6 Thermal 13.2 9.67 12.7 conductivity W/mK Pr 0.0238 0.022 0.022 C p J/kg-K 190 139.5 146.5 P. Satyamurthy, December 21-23, 2009-IITK
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 ) Scale down Mercury TBM T i = 380 0 C, Actual TBM v =0.1m/s P. Satyamurthy, December 21-23, 2009-IITK
Proposed Mercury facility for MHD studies (Ha ~6000, N ~2000, Re ~15,000) Cooling HX tower Coil Pump water supply in. Control Valve Flow meter BGV Magnet~2 Mercury- T Dump TBM Tank P. Satyamurthy, December 21-23, 2009-IITK
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