ELECTROMAGNETIC LIQUID METAL WALL PHENOMENA

Similar documents
Summary of Thick Liquid FW/Blanket for High Power Density Fusion Devices

Experimental Facility to Study MHD effects at Very High Hartmann and Interaction parameters related to Indian Test Blanket Module for ITER

Hydrogen and Helium Edge-Plasmas

Adaptation of Pb-Bi Cooled, Metal Fuel Subcritical Reactor for Use with a Tokamak Fusion Neutron Source

The Dynomak Reactor System

0 Magnetically Confined Plasma

Simple examples of MHD equilibria

Yuntao, SONG ( ) and Satoshi NISHIO ( Japan Atomic Energy Research Institute

Passive, Active and Feedback Stabilization of Thick, Flowing Liquid Metal Walls

3D MHD SIMULATION UPDATE

Fusion/transmutation reactor studies based on the spherical torus concept

Imposed Dynamo Current Drive

Introduction to Fusion Physics

Numerical study of liquid metal film flows in a varying spanwise. magnetic field

Liquid Metal Flow Control Simulation at Liquid Metal Experiment

Compact, spheromak-based pilot plants for the demonstration of net-gain fusion power

ARIES-AT Blanket and Divertor Design (The Final Stretch)

FLIBE ASSESSMENTS ABSTRACT

Status of the Concept Design of CFETR Tokamak Machine

Validation Of COMSOL Multiphysics For Magneto-hydro-dynamics (MHD) Flows In Fusion Applications

The Path to Fusion Energy creating a star on earth. S. Prager Princeton Plasma Physics Laboratory

Physics of fusion power. Lecture 14: Anomalous transport / ITER

Material, Design, and Cost Modeling for High Performance Coils. L. Bromberg, P. Titus MIT Plasma Science and Fusion Center ARIES meeting

Observations of Thermo-Electric MHD Driven Flows in the SLiDE Apparatus

Implementation of a long leg X-point target divertor in the ARC fusion pilot plant

Formation and Long Term Evolution of an Externally Driven Magnetic Island in Rotating Plasmas )

Studies of Next-Step Spherical Tokamaks Using High-Temperature Superconductors Jonathan Menard (PPPL)

GA A22689 SLOW LINER FUSION

Possibilities for Long Pulse Ignited Tokamak Experiments Using Resistive Magnets

Role and Challenges of Fusion Nuclear Science and Technology (FNST) toward DEMO

A SUPERCONDUCTING TOKAMAK FUSION TRANSMUTATION OF WASTE REACTOR

Concept of Multi-function Fusion Reactor

CHALLENGE: MAGNETOHYDRODYNAMICS

INTRODUCTION TO MAGNETIC NUCLEAR FUSION

FLIHY constructed as a flexible facility that serves many needs for Free-Surface Flows in low-k, high Pr fluids

2. FLUID-FLOW EQUATIONS SPRING 2019

Toroidal flow stablization of disruptive high tokamaks

The Status of the Design and Construction of the Columbia Non-neutral Torus

Improved Magnetic Fusion Energy Economics Via Massive Resistive Electromagnets

Chapter IX: Nuclear fusion

Perspective on Fusion Energy

Conceptual Design of Advanced Blanket Using Liquid Li-Pb

Recent Development of LHD Experiment. O.Motojima for the LHD team National Institute for Fusion Science

Turbulence and Transport The Secrets of Magnetic Confinement

Magnetohydrodynamic Flow of a Liquid Metal in a Curved Circular Duct subject to the Effect of an External Magnetic Field

MHD Analysis of Dual Coolant Pb-17Li Blanket for ARIES-CS

MAGNETOHYDRODYNAMICS

Overview of Pilot Plant Studies

MHD. Jeff Freidberg MIT

Fusion Nuclear Science - Pathway Assessment

MHD problems in free liquid surfaces as plasma-facing materials in magnetically confined reactors

Toward the Realization of Fusion Energy

Transmutation of Minor Actinides in a Spherical

Design of next step tokamak: Consistent analysis of plasma flux consumption and poloidal field system

Fusion: The Ultimate Energy Source for the 21 st Century and Beyond

EU PPCS Models C & D Conceptual Design

Study on supporting structures of magnets and blankets for a heliotron-type type fusion reactors

Highlights from (3D) Modeling of Tokamak Disruptions

GA A23168 TOKAMAK REACTOR DESIGNS AS A FUNCTION OF ASPECT RATIO

Polywell Fusion J A E YO UNG PA R K E NN F USION SYMPOSIUM, A P R I L

A Faster Way to Fusion

STABILITY ANALYSIS FOR BUOYANCY-OPPOSED FLOWS IN POLOIDAL DUCTS OF THE DCLL BLANKET. N. Vetcha, S. Smolentsev and M. Abdou

Der Stellarator Ein alternatives Einschlusskonzept für ein Fusionskraftwerk

Heat Flux Management via Advanced Magnetic Divertor Configurations and Divertor Detachment.

MAGNETIC NOZZLE PLASMA EXHAUST SIMULATION FOR THE VASIMR ADVANCED PROPULSION CONCEPT

CFD simulation of the magnetohydrodynamic flow inside the WCLL breeding blanket module

Tokamak Fusion Basics and the MHD Equations

Magnetohydrodynamic stability of negative central magnetic shear, high pressure ( pol 1) toroidal equilibria

Observation of Neo-Classical Ion Pinch in the Electric Tokamak*

purposes is highly encouraged.

FLOW ANALYSIS IN THE HCLL-TBM ITER CHANNELS INCLUDING MHD AND HEAT TRANSFER

NIMROD Boundary Conditions

Design optimization of first wall and breeder unit module size for the Indian HCCB blanket module

Local organizer. National Centralized Tokamak

Conceptual design study for heat exhaust management in the ARC fusion pilot plant

Resistive Wall Mode Control in DIII-D

Design of structural components and radial-build for FFHR-d1

MELCOR Analysis of Helium/Water/Air Ingress into ITER Cryostat and Vacuum Vessel

PFC/JA NEUTRAL BEAM PENETRATION CONSIDERATIONS FOR CIT

Simulation of alpha particle current drive and heating in spherical tokamaks

Understanding physics issues of relevance to ITER

Developing a Robust Compact Tokamak Reactor by Exploiting New Superconducting Technologies and the Synergistic Effects of High Field D.

Helium Catalyzed D-D Fusion in a Levitated Dipole

Behavior of Compact Toroid Injected into the External Magnetic Field

Current-driven instabilities

MHD Stabilization Analysis in Tokamak with Helical Field

Spherical Torus Fusion Contributions and Game-Changing Issues

Control of Sawtooth Oscillation Dynamics using Externally Applied Stellarator Transform. Jeffrey Herfindal

Nuclear Energy in the Future. The ITER Project. Brad Nelson. Chief Engineer, US ITER. Presentation for NE-50 Symposium on the Future of Nuclear Energy

Design concept of near term DEMO reactor with high temperature blanket

SOME CONSIDERATION IN THE TRITIUM CONTROL DESIGN OF THE SOLID BREEDER BLANKET CONCEPTS

generalfusion Characterization of General Fusion's Plasma Devices 2015 Nimrod Summer Workshop

Experimental Study of Hall Effect on a Formation Process of an FRC by Counter-Helicity Spheromak Merging in TS-4 )

Unpressurized steam reactor. Controlled Fission Reactors. The Moderator. Global energy production 2000

W.A. HOULBERG Oak Ridge National Lab., Oak Ridge, TN USA. M.C. ZARNSTORFF Princeton Plasma Plasma Physics Lab., Princeton, NJ USA

The Linear Theory of Tearing Modes in periodic, cyindrical plasmas. Cary Forest University of Wisconsin

Non-Solenoidal Plasma Startup in

Mission Elements of the FNSP and FNSF

(a) (b) (c) (d) (e) (f) r (minor radius) time. time. Soft X-ray. T_e contours (ECE) r (minor radius) time time

Tritium Control and Safety

Transcription:

ELECTROMAGNETIC LIQUID METAL WALL PHENOMENA BY BOB WOOLLEY 15-19 FEBRUARY 1999 APEX-6 MEETING

LIQUID WALLS A sufficiently thick, flowing, liquid first wall and tritium breeding blanket which almost completely surrounds a fusioning tokamak DT plasma could provide superior features in a commercial MFE powerplant. Much of the costly complexity of conventional solid first wall designs would be eliminated. It would eliminate first wall damage from neutrons, from high heat flux, and from disruptions. Power density would not be limited by damage issues, so higher power density may be possible. It would eliminate solid surface tritium inventories which are not accessible. If sufficiently thick (> 1 m lithium), it would eliminate the need to develop exotic structural materials more resistant to neutron damage. If sufficiently thick (> 1 m lithium), it would reduce the activation and waste disposal requirements for structural materials.

LIQUID WALLS A nonconducting or poorly conducting liquid material containing lithium such as the molten salt, FLiBe, could provide a liquid first wall&breeding blanket with minimal MHD interactions. Centrifugal force would need to be used to keep it out of the plasma. However, use of molten lithium could also bring other benefits: Lithium is a ZERO activation material, and is not especially toxic. Lithium is low-z (after hydrogen and helium) and so could be expected to have small impact on plasma radiation losses. Experience and some theory suggest lithium impurities may improve plasma performance. Lithium walls could reduce vacuum pumping problems. Use of a single element may simplify chemical processing of the blanket. Lithium could also be used for direct LMMHD production of electricity, using the TF magnets as the LMMHD power production magnets, further reducing capital costs for a fusion power plant.

LMMHD POWER GENERATION BASIC LMMHD CONVERSION CYCLE DIAGRAM USING REGENERATIVE HEAT EXCHANGER gas MIXER froth SEPARATOR HEAT SOURCE MHD GENERATOR MHD PUMP liquid liquid gas REGENERATIVE HEAT EXCHANGER COMPRESSOR REJECT HEAT

LMMHD POWER GENERATION ANL S 1972 REPORT* FOR US NAVAL RESEARCH PROPOSED THESE LITHIUM/HELIUM DESIGN PARAMETERS: INPUT TEMPERATURE 871 C REJECT TEMPERATURE 16 C THERMAL HEAT INPUT 72 MW () ELECTRICAL POWER OUTPUT 30 MW (EL) 0.75 Tesla 0.9 m ELECTRICAL VOLTAGE OUTPUT 20 VDC ELECTRICAL CURRENT OUTPUT 1.5 MA LITHIUM MASS FLOW RATE 2217.6 KG/S HELIUM MASS FLOW RATE 31.7 KG/SEC FLOW VELOCITY 30 M/S MHD GEN. MAGNETIC FIELD 0.75 TESLA MHD GEN. PRESSURE IN 75 ATM. MHD GEN. PRESSURE OUT 25 ATM. MHD GEN VOID FRACTION IN 64 % MHD GEN VOID FRACTION OUT 84 % 0.4 m 30 m/s 0.9 m 9 m ANL s PROPOSED 30 MEGAWATT ELECTRIC LMMHD GENERATOR DUCT PARAMETERS (APPROXIMATE) Petrick Project Scientist *by W.Amend et al, M.

ELECTROMAGNETIC INTERACTIONS(1) However, use of a thick liquid metal wall with a tokamak introduces electromagnetic LMMHD interactions. LOW PRESSURE DROP (The good news) is that LMMHD pressure drop losses are entirely missing from axisymmetric flows parallel to the symmetry axis of a purely toroidal field, with no electrical connection between inner and outer duct walls. Such axisymmetric ducts do not need insulation coatings. NEED TO FOLLOW POLOIDAL FLUX If liquid metal flow in a poloidal plane cuts across poloidal flux lines, the resulting V X B electric field will produce a toroidal current locally in the liquid metal, which in turn will modify the poloidal field needed for plasma equilibrium. It therefore seems necessary to design the LM flow path following poloidal flux lines near the plasma s last closed flux surface. If liquid metal flow follows paths near poloidal flux lines in a poloidal plane, it will typically not be moving in a purely vertical direction, but will have a radial velocity component.

ELECTROMAGNETIC INTERACTIONS(2) DIAMAGNETIC DRAG The radial component of LM velocity through the toroidal field will introduce a diamagnetic drag force opposing that radial motion. For outward radial motions the toroidal magnetic flux trapped in a liquid metal s constant volume shrinking cross section is compressed and stretched. At the same time, the 1/R toroidal magnetic flux density outside the liquid metal is lower at the larger major radius. This imbalance produces the diamagnetic drag opposing LM motion. The same process also opposes inwards motions. The strength of the diamagnetic drag effect depends on how rapidly the flux imbalance diffuses away. The parameter, λ= 1/µ 0 σ = 0.36 s m -2, predicts magnetic diffusion through 1.7 meters of lithium in one second. The strength of the drag varies strongly with the vertical extent of the liquid metal and with its shape. (It seems to be inherently two-dimensional.) Some simple approximate formulas have been derived for very thin layers, but have not been confirmed.

ELECTROMAGNETIC INTERACTIONS(3) INJECTED POLOIDAL CURRENT In order to oppose the diamagnetic drag force, poloidal current is injected into the flowing liquid metal. DC Power Supply Vps - + Liquid Metal Inlet PF Coils Eemf Solid Conductor Flowing Liquid Metal Free Surface S PF PF Coils Vacuum or Plasma Region S PF Center Line TF Coil Liquid Metal Outlet

ELECTROMAGNETIC INTERACTIONS(4) INJECTED POLOIDAL CURRENT. The injected poloidal current needs to closely follow the poloidal field direction in order to avoid a toroidal swirl motion in the liquid metal. MAGNETIC PROPULSION OF LM (IDENTIFIED BY L. ZAKHAROV) Nonuniformity of J X B produced by the injected poloidal current and toroidal field produces a pressure gradient along the solid wall located behind the liquid. This pressure gradient will tend to move the LM towards increasing major radius. With thin layers, use of high currents may result in high speed free surface flows. With thicker layers and less intense currens, it may still be significant phenomenon. FREE SURFACE SHAPE The shape of the free surface will not necessarily be of uniform layer thickness. The free surface shape results from interplay of flow parameters in a way not yet known. It is expected sensitive to injected current strength, injected fluid speed, and shape of backing surface.

COMPUTER SIMULATION STATUS Not yet working. But very close. Coded in DEC-extended Fortran, residing on PPPL s VAX cluster. Unstructured grid code is completely tested, including a solution adaptive grid point migration algorithm. Galerkin gradient tested; this permits mixed finite element method with piecewise linear elements to be used for any order evolution PDE via explicit integration. Now testing PPE; minor glitches with non-dirichlet BCs. Some PPL physicists have volunteered to help with evaluation testing (after it produces some intelligible output).

AXISYMMETRIC LM EXPERIMENT Symbol Name Expanation Formula Fr Froude Number Inertial Force Density U gl Gravitational Force Density EmGd EmGd Number Driven EM Force Density (new) EmGp (new) Rm EmGp Number Gravitational Force Density Passive EM Force Density Gravitational Force Density Magnetic Reynolds Number Induced Magnetic Field Applied Magnetic Field Ha Hartmann Number Passive EM Force Density Viscous Force Density We Weber Number Inertial Force Density Re =Ha 2 Fr 2 /Wp S (aka N) =Wp/Fr 2 Reynolds Number Stuart Number akainteractionparameter Surface Tension Force Density Inertial Force Density Viscous Force Density Passive EM Force Density Inertial Force Density B 0 ( B LM ) ρgµ 0 L σ ρg B 2 0 U µ 0 σ vl B 0 L ρ γ U2 L UL ν σ ρν σ B 2 0 L ρ U A small collaborative tabletop experiment would be useful. Experiment should have a toroidal field magnet system, an axisymmetric chamber, a liquid metal, and flow diagnostics.