Experimental Facility to Study MHD effects at Very High Hartmann and - - PowerPoint PPT Presentation

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Experimental Facility to Study MHD effects at Very High Hartmann and - - PowerPoint PPT Presentation

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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. Satyamurthy Bhabha Atomic Research Centre, India P. Satyamurthy, December 21-23, 2009, IITK Team

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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. Satyamurthy

Bhabha Atomic Research Centre, India

  • P. Satyamurthy, December 21-23, 2009, IITK
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SLIDE 2

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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SLIDE 4

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)

Deuterium Neutron Tritium Helium

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
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SLIDE 5

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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SLIDE 6

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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SLIDE 7

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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SLIDE 8

Tritium Breeding

Natural lithium: 7.42% 6Li and 92.58% 7Li Required: 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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SLIDE 9

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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SLIDE 10

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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SLIDE 11

11

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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SLIDE 12

12

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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SLIDE 14

14

High grade heat extraction Radiation Shielding

BLANKET Functions

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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SLIDE 18

18

Indian TBM System

  • P. Satyamurthy, December 21-23, 2009-IITK
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SLIDE 19
  • 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 Radial 536 mm Toroidal 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 Wall Loading 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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SLIDE 23

MHD Effects in TBM

  • P. Satyamurthy, December 21-23, 2009, IITK
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SLIDE 24

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

  • pposing 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

  • r

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

  • 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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SLIDE 26

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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SLIDE 30

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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SLIDE 31

MHD Effects on Turbulence

  • P. Satyamurthy, December 21-23, 2009-IITK
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SLIDE 32

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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SLIDE 33

Combined Forced & Natural Convection - Buoyancy Effects

+ Suitable Turbulent Model

  • P. Satyamurthy, December 21-23, 2009-IITK
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SLIDE 34

Poloidal- y Flow Uy -Downwords Flow Uy - Upwards Flow -L bend Ux Uy – L-bend Under 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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SLIDE 35

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 0.022 Cp J/kg-K 190 139.5 146.5

  • P. Satyamurthy, December 21-23, 2009-IITK
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SLIDE 37

Scale down Mercury TBM Actual TBM

B = 4T Pb 83%-Li -17% (enriched 90% of Li6 ) Ti = 380 0C, v =0.1m/s 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

  • P. Satyamurthy, December 21-23, 2009-IITK
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SLIDE 38

Proposed Mercury facility for MHD studies (Ha ~6000, N ~2000, Re ~15,000) Pump Dump Tank HX Mercury- TBM Coil Magnet~2 T Control Valve Flow meter BGV Cooling tower water supply in.

  • P. Satyamurthy, December 21-23, 2009-IITK
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SLIDE 39
  • 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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SLIDE 40

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 wall 1.62 × 0.424 59 ~ 43 ~ 6.9 Top & Bottom wall 0.436 × 0.424 33.6 7.0 ~ 2.8 (for each wall) Right & Left wall 1.62 × 0.436 66.8 23.64 ~ 5.1 (for each wall) First Solid Breeder 1.4746 × 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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SLIDE 41

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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SLIDE 42

Process details of the Facility

  • P. Satyamurthy, December 21-23, 2009-IITK
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SLIDE 43

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