experimental facility to study mhd effects at very high hartmann...
TRANSCRIPT
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Experimental Facility to Study MHD effects at Very High Hartmann and Interaction parameters related
to Indian Test Blanket Module for ITER
P. SatyamurthyBhabha Atomic Research Centre, India
P. Satyamurthy, December 21-23, 2009, IITK
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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
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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
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Origin of Nuclear Fusion Energy
Illustration from DOE brochure
17.6 MeV 80% of energy release (14.1 MeV)
Used to breed tritium and close the DT fuel cycle
Li + n → T + He
20% of energy release (3.5 MeV)
DeuteriumNeutron
Tritium Helium
Deuterium and tritium is the easiest, attainable at lower plasma temperature, because it has the largest reactionrate and high Q value and hence the program is focused on the D-T Cycle
Ref: Prof. Abdou, UCLAP. Satyamurthy, December 21-23, 2009, IITK
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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
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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
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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
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Tritium Breeding
Natural lithium: 7.42% 6Li and 92.58% 7LiRequired: 90% 6Li and 10% 7Li
6Li (n,α) t
7Li (n;n’α) t
P. Satyamurthy, December 21-23, 2009-ITK
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Neutron Multipliers for Fusion Energy Growth
Desired characteristics:– Small absorption cross-sections
– Large (n, 2n) cross-section with low threshold
• Candidates:– Beryllium is the best (large n, 2n with low threshold, low absorption)
–Pb is most effective in Li-Pb eutectic
9Be (n,2n) Pb (n,2n)
Candidates - Beryllium, Lead
P. Satyamurthy December 21-23, 2009-IITK
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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
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THE ITER DEVICE
Parameters
Height: 25 m, Diameter: 28 m
Total Fusion Power 500 MW
Q- Fusion Power /Auxiliary heating power
≥ 10
Average Neutron wall loading 0.57 MW/m2
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 m3
Neutrons Generated 1.5 x 1020 n/s
International Thermonuclear Experimental Reactor
P. Satyamurthy, December 21-23, 2009-IITK
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Typical DEMO Reactor
P. Satyamurthy, December 21-23, 2009-IITK
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Plasma
Radiation
Neutrons
Coolant for energy conversion
First Wall
Shield
Blanket Vacuum vessel
Magnets
Tritium breeding zone
Major Sub-systems of ITER
P. Satyamurthy, December 21-23, 2009-IITK
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High grade heat extraction
Radiation Shielding
BLANKETFunctions
Tritium Breeding
P. Satyamurthy, December 21-23, 2009-IITK
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ITER is a collaborative effort among Europe, Japan, US, Russia, China, South Korea, and India
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ITER Location- Caradache (France)
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Typical ITER-TBM (proposed by US)
Vacuum Vessel
Bio-shield
A PbLi loop Transporter located in
the Port Cell Area
He pipes to TCWS
2.2 m
TBM System ( Heat Extraction from Neutrons & First wall radiation + T Breeding)
• 3 ITER equatorial ports (1.75 x 2.2 m2) for TBM testing
• Each port can accommodate only 2 modules (i.e. 6 TBMs max)
P. Satyamurthy, December 21-23,2009-IITK
Typical TBM System
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Indian TBM System
P. Satyamurthy, December 21-23, 2009-IITK
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First wall Top-bottom plate assembly Breeder assembly Inner back plate Outer back plate Manifolds and pipes Flexible housings and support
keysPoloidal 1660 mm
Radial 536 mmToroidal 480 mm
Indian Lead-Lithium cooled Ceramic Breeder (LLCB) TBM
P. Satyamurthy, December 21-23, 2009-IITK
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Details of Indian TBM
P. Satyamurthy, December 21-23, 2009-IITK
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Flow Configuration – Indian LLCB TBM
P. Satyamurthy, December 21-23, 2009-IITK
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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 Material
Be coating (~2 mm)
Structural material RAFMS
Breeder PbLi, Li2TiO3
Neutron WallLoading
2.42 MW/m2 (0.78MW/m2 )
Total Power Deposition
2.24 MW (0.857 MW)
Average. Heat Flux 0.5 MW/m2
Primary Coolant PbLi and Helium P. Satyamurthy, December 21-23, 2009-IITK
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MHD Effects in TBM
P. Satyamurthy, December 21-23, 2009, IITK
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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 (JxBo)
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 directionY-Induced currentZ- Applied Magnetic FieldWalls perpendicular to B-Hartmann wallsWalls parallel to B – side walla
P. Satyamurthy, December 21-23, 2009-IITK
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Equations Governing Flow in TBM
P. Satyamurthy, December 21-23, 2009-IITK
3-D MHD-CFD code is being developed 1) ANUPRAVAHA –IIT-BARC Code (Prof. Eswaran,IITK) 2) M/s Fluidyne (Bangaluru)
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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
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Hartmann-effect
Increasing Hartmann Number
P. Satyamurthy, December 21-23,2009-IITK
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MHD effects-‘M’ profiles Across Side walls
uaverage = 0.036 m/s
σ s i d e = 0 , σHWall=∞
σ s i d e = ∞ , σHWall=∞
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Effect of transverse B variation
- Transition to M-Profile (strong function of N)
-Generation of additional currents
P. Satyamurthy, December 21-23,2009-IITK
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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
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MHD Effects on Turbulence
P. Satyamurthy, December 21-23, 2009-IITK
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2-D MHD Turbulence Ref: Smolentsev et al
Vorticity Distribution-Ha/Re>>1/300
P. Satyamurthy, December 21-23, 2009-IITK
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Combined Forced & Natural Convection - Buoyancy Effects
+ Suitable Turbulent Model
P. Satyamurthy, December 21-23, 2009-IITK
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Polo
idal
- y
Flow Uy -Downwords
Flow Uy - Upwards
Flow -L bend
Ux Uy – L-bendUnder Developed Flow - Transient Region
, Geometry change
Radial-x
Bz Toroidal
Flow complexity in TBM
Toroidal-z
Flow - U bend
Uy Ux Uy
Ux P. Satyamurthy, December 21-23, 2009-IITK
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Experimental Programme to Study MHD Phenomena in TBM
P. Satyamurthy, December 21-23, 2009-IITK
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Similarities of Pb-Li, Hg and Pb-Bi liquid metals
Properties Pb-Li(300 0C)
Hg(50 0C)
Pb-Bi
Density kg/m3 9500 13352 10360
Electrical Conductivity mho/m
0.77x106 1.02x106 ~1.0x106
Viscosity m2/s 0.188x10-6 0.116x10-6 .187x10-6
Thermal conductivity W/mK
13.2 9.67 12.7
Pr 0.0238 0.022 0.022Cp J/kg-K 190 139.5 146.5
P. Satyamurthy, December 21-23, 2009-IITK
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Scale down Mercury TBMActual TBM
B = 4TPb 83%-Li -17% (enriched 90% of Li6 )Ti = 380 0C, v =0.1m/s
TBM Mercury-TBMB ~4T ~2.0-1.8 THa ~18500 ~6000Re ~ 50,000 ~24500N ~ 6700 ~1200 Ha/Re ~0.36 ~0.22
P. Satyamurthy, December 21-23, 2009-IITK
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Proposed Mercury facility for MHD studies (Ha ~6000, N ~2000, Re ~15,000)
Pump
Dump Tank
HX
Mercury-TBM
Coil
Magnet~2T
Control Valve
Flow meter
BGV
Cooling tower water supply in.
P. Satyamurthy, December 21-23, 2009-IITK
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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
Major components of the MHD-TBM Simulation Facility
P. Satyamurthy, December 21-23, 2009-IITK
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Heat deposition area of LLCB TBM (m2 )
Heat generation in LLCB TBM Walls (kW)
Surface heat flux (kW/m2)
Heat to be supplied in Mercury TBM for heat flux simulation (kW)
First wall1.62 × 0.424
59 ~ 43 ~ 6.9
Top & Bottom wall0.436 × 0.424
33.6 7.0 ~ 2.8(for each wall)
Right & Left wall1.62 × 0.436
66.8 23.64 ~ 5.1(for each wall)
First Solid Breeder1.4746 × 0.424
42.2 33.75~ 9.0
Second Solid breeder 1.4746 × 0.424
31.3 25.0 ~ 6.7
Third Solid Breeder 1.4746 × 0.424
18.4 14.71 ~ 2.0
Simulation of Nuclear Heat and Solid Breeder Heat Generation in Mercury-TBM
P. Satyamurthy, December 21-23, 2009-IITK
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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
Diagnostics in the Mercury-TBM
P. Satyamurthy, December 21-23, 2009-IITK
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Process details of the Facility
P. Satyamurthy, December 21-23, 2009-IITK
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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
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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
P. Satyamurthy, December 21-23, 2009-IITK
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Thank You
P. Satyamurthy, December 21-23, 2009-IITK