Download - HST Eagle Nebula
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Fusion and Plasma Physics are at the Core of Nature's Most Powerful Self-Driven Systems
CHANDRA
Cassiopia A
HST
Eagle Nebula
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Can we Solve the Mystery of Producing a Stationary Self-Sustained Fusion Fire??
CHANDRA
Crab Nebula
SOHO
VLBA
Galactic Jet - M87
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Confining a Fusion Fire
A Grand Challenge for Science and Technology
Dale Meade
Princeton University
Presented at
Department of Aeronautics and Astronautics
University of Washington, Seattle, WA
http://fire.pppl.gov November 19, 2001 http://www.cpepweb.org
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Fusion is an Outstanding Physics Challengeand is Connected to Other Outstanding Challenges
December 1999 DMM• Quantum gravity presents the ultimate challenge to theorists
• Explaining high-Tc superconductors
• Unstable nuclei reveal the need for a complete theory of the nucleus
• Realizing the potential of fusion energy
• Climate prediction is heavy weather
• Turbulence nears a final answer
• Glass physics: still not transparent
• Solar magnetic field poses problems
• Complexity, catastrophe and physics
• Consciousness: the physicists view
Ten Outstanding Physics Challenges
DMM
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SOHO
Fusion Does Work at Large Size
Why is it so difficult in the lab?
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Relevant Reactions for Fusion in the Laboratory
D+ + D
+ ––>
3He++ (0.82 Mev) + n
0 (2.5 MeV)
––> T+
(1 MeV) + p+
(3 MeV)
D+
+ 3He++ ––>
4He++ (3.6 MeV) + p
+ (14.7 MeV)
D+
+ T+
––> 4He++ (3.5 MeV) + n
0 (14.1 MeV)
Li6 + n ––>
4He (2.1 MeV) + T (2.7 Mev)
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Fusion Cross Sections and Reaction Rates
For Example: PDT = nD nT <σv> (Uα + Un)
= 5.6 x 10 -7 <σv> nD nT watts m-3 , note: <σv> ~ T2 @ 10 keV
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Energy/Fuel
Recovery
Qp
Fuel
Fuel (Li, D)
ηRPE
Waste
PE
Balance of Plant
Plasma Confinement and External
Heating
Key Plasma Performance Metrics • Fusion Gain (Qp) • Fusion Energy Density • Duty Cycle/Repetition Rate
The Grand Challenge, Science and Technology for Fusion
Blanket
Key Engineering Metrics • First Wall Lifetime • Availability/Reliability • Environment and Safety • System Costs
First Wall
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There are Three Principal Fusion Concepts
Toroidal Magnetic
surface of helical B lines
twist of helix
twist profile
plasma profile
toroidal symmetry
V
r
Reactivity Enhancement
muon catalysis
polarized nuclei
others?
Spherical Inertial
gravitational
transient compression
drive (laser-D/I, beam)
radial profile
time profile
electrostatic
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Plasma Requirements for a Burning Plasma
Power Balance
Paux-heat + n2 <σv> UαVp/4 - CBT1/2ne2Vp
= 3nkTVp/τE + d(3nkTVp)/dt
where: nD = nT = ne/2 = n/2, n2 <σv> UαVp/4 = Pα is the alpha heating power,
CBT1/2ne2Vp
is the radiation loss, Wp = 3nkTVp and
τE = Wp/(Paux-heat - dWp/dt) is the energy confinement time.
In Steady-state:
nτE = 3kT
<σv> Uα (Q+5)/4Q - CBT1/2
where Q = Pfusion/ Paux-heat
Q = 1 is Plasma Breakeven, Q = ∞ is Plasma Ignition
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100
10
1
0.10
0.01
0.1 1 10 100CENTRAL ION TEMPERATURE, T (0) (keV)
Status of Laboratory Fusion Experiments
i
LA
WS
ON
PA
RA
ME
TE
R, n
(10
m
s)
it E20
-3
#97GR041.ntau-98 FIRE
D-T
D-D
Legend
JET
Q =1DT Ignition
TFTR
ALCC
JET
TFTRALCA
PLT
T10
DIII JT60
PLTTFR
TFR
T3
DIII-D
ATC
JET
JT-60U
JT-60U
Moderate Density Magnetic
Higher Density Magnetic
DIII-D
DIII-D
JETFT
ITER
Ignitor, CIT, FIRETFTR
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Comparison of Typical Plasma Parameters forInertial and Magnetic Fusion
Inertial Magnetic
Ti (keV) 10 10
n (m-3) 6 x 1030 3 x 1020
τE (sec) 10-10 2
radius (m) 10-4 1
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Why is Confinement a Challenge for Magnetic Fusion?
A D-T reactor at a fuel density of 1020 m-3 requires
E ~ 1 second , Ti ~ 10 keV
Te ~ 10 keV vte ~ 6 x 107 m/s
Assume a container with
radius ~ 1 m (typical radius for a magnetic bottle)
Then the number of bounces
N ~ vte / r ~ 6 x 107
~ 30 coulomb collisions under typical conditions
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Toroidal Magnetic Chamber (Tokamak)
Axisymmetric Magnetic Configuration • axial current, IT , produces toroidal magnetic field, BT • toroidal current, Ip , produces vector potential, Aφ and poloidal field, Bp
Axisymmetry ensures that: • magnetic field lines lie in nested magnetic surfaces given by ψ = 2πRAφ • charged particles are confined to within δ of magnetic surface due to conservation of canonical angular momentum
q = field line cycles long way (toroidally) for one one cycle short way(poloidally)
2mH = pR2 + pZ
2 + (pφ - eRAφ)2 + eΦ(R,Z)
R2δ ~ mv/eBp
Ip
IT
•
•
•
0,3
1
2
Bp
BT
q > 1 tokamak configuration•
•
•
0'
1'
2'
Ip produced by inductive drive orpressure driven boostrap current.
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Toroidal Asymmetry can cause plasma loss
• small magnetic field perturbations can have large effect at resonant surfaces
• particle collisions (would allow present tokamaks to be near ignition) • plasma instabilities (main limit in present fusion devices)
Ip
IT
Nested Magnetic Surfaces (ψ = constant)
Plasma pressure = f(ψ)
q = q(ψ)
Toroidal Magnetic Confinement
projection of single particle orbit
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Tokamak Fusion Test Reactor
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Tokamak Fusion Test Reactor
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095–99 (modified DMM)
Comprehensive Diagnostic Systems have been Developed to Investigate Fusion Plasmas
● Equilibrium magnetics
● Core profile diagnosticsne, ni, Ti, Te, Zeff, Zi, v
● Internal magnetic field profile, Bθ, q
● Core and edge turbulence ne, Te
● Edge and divertor Te, ne, Ze, radiation,
~ ~
Spatially and Time Resolved
Beam
FluxSurfaces
neutral pressure
— Typically ~50 diagnostic measurements
Detection
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Plasma Instabilities Limit Fusion PlasmaConfinement
Small-Scale Electrostatic Turbulence (fluctuating electric field, δE)
v = δExB/B2, ions and electrons both drift across the magnetic fieldpreserving charge neutrality
λ > ρi instability wavelength ~ ion gyro-radius
∆ ~ v τ correlation random walk step size
Small-Scale Magnetic Turbulence (fluctuating magnetic field, δB)
v = vthermalδB/B, mainly loss of electron energy
Large-Scale Large-Amplitude Magnetic Instability
plasma pressure sufficient to distort even tear the magnetic field, similar to solar flares. Can cause total loss of plasma in a tokamak.
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MMMMaaaaggggnnnneeeettttiiiicccc FFFFuuuussssiiiioooonnnn EEEEnnnneeeerrrrggggyyyy
FUSION POWER IS DETERMINED BY
MACROSCOPIC STABILITY
• Plasma stability is largely determined by
βµ
≡ 222
0
nT
B /
• Fusion power
• Denser, hotter plasma makes more fusion.
p E n n v n T Bfus fus d t fus= σ β~ ~2 2 2 4
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Simulation of a Plasma Disruption Driven by High Plasma Pressure
Nonlinear 3-D Fluid Computation
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Plasma Science Areas in Magnetic Fusion
• Macroscopic Stability
• Wave-particle Interactions
• Transport and Microturbulence
• Plasma-wall Interactions
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Wind Tunnel Experiments on Plasma Confinement
ωcτρ* = ρ/aν* = νc/νbβ
Dimensionless Parameters ITER-EDA
ITER-FEATXX
FIRExx
BτEth
BτEth ~ ρ*–2.88 β –0.69 ν* –0.08
Similarity Parameter
B R 5/4
Kadomtsev, 1975
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Measured Transport isMuch Larger than Neoclassical Transport
χeneo
smallerby ~60
χ ≡ - q⊥ / n ∇T
• Wrong profile, scaling with B and collisionality• Better than no magnetic field by 106
• Additional processes: turbulence
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University of Wisconsin-MadisonDepartment of Engineering Physics
Localized Turbulence Measured via BESBeam Emission Spectroscopy: measure local density turbulence fromfluctuations in light emitted from injected neutral H0 beam:
BES Viewing Geometry
Viewport
(105o)
DIII-D Tokamak Top View
Core Channels
Edge Channels
Neutral BeamSource
(150o Beamline)
Z (
m)
Poloidal Cross Section
Major Radius, R (m)
Expanded View
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Showing Turbulent Eddies in TFTR
Heat Flow
• δn/n ~ 0.1 %, δTi/Ti ~ 3-4 δn/n, λ >> ρi , λradial >> λpoloidal• Consistent with simulations of ion temperature gradient (ITG) instabilities
PlasmaCenter
PlasmaEdge
polo
idal
(ve
rtic
al)
dire
ctio
n
radial direction
Contours of equi-density
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Understanding Turbulent Plasma Transport⇒ An important problem:
⇒-- Size of plasma ignition experiment determinedby fusion self-heating versus turbulent transportlosses
⇒-- Dynamics also of interest to other fields (e.g.,astrophysical accretion disks)
⇒ A scientific Grand Challenge problem
⇒
⇒ A true terascale computational problem for MPP’s
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Full Torus Simulations of Turbulent Transport Scaling
• Large-scale full torus gyrokinetic particle simulations for device-size scans• Global field-aligned mesh (GTC code) saves factor ~100 in computation• Efficient utilization of new 5 TF IBM SP @ NERSC (just available 8/01) -- fastest non-classified supercomputer in world• Most recent simulations used 1 billion particles (GC), 125 M spatial grid points, and 7000 time steps --- leading to important (previously inaccessible) new results
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Flu
ctua
tion
leve
l δn
/n (
%)
Gro
wth
, she
arin
g ra
tes
(105
s-1 )
W. Lee, Z. Lin, E. Mazzucato, E. Synakowski, M. Beer
Experiment Gyrokinetic Simulations
• Turbulent eddies disrupted by strongly sheared plasma flow
• Bursts of fluctuations are suppressed when E×B shearing rate exceeds growth rate of most unstable mode
WithoutFlow
WithFlow
PRINCETON PLASMA PHYSICS LABORATORY
PPPLE. Mazzucato et al, PRL 77 (1996) 3145
Z. Lin et al, Science 281 (1998) 1817
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χχχχ i a /ρ
i2 vi
a / ρi
Full Torus Simulations of Turbulent Transport Scaling
• Transport driven by microscopic scale fluctuations (ITG modes) in presentdevices can change character: transition from Bohm-like scaling ~ (ρIvi ) toLarmor-orbit-dependent “Gyro-Bohm” scaling ~ (ρivi )(ρI/ a)
• “Rollover” is good news ! (since simple extrapolation is pessimistic)
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October., 1999Wesley Smith, U. Wisconsin
b quark
LHC
Accelerators
hadron
electron
SLC
Prin-Stan
ISR
SPEAR
CESR
TRISTAN
SppS
Tevatron
PEP
s quark
c quark
W, Z bosons
Higgs boson
LEPII t quark
1970 1980 1990 2000
1 GeV
10 GeV
100 GeV
1TeV
High Energy Physics Accelerators Enable Discovery
High Energy Physics Accelerators Enable Discovery
HEP facilities plotted by discovery reach in mass vs. year
Also shown are some important discoveries and the expected range for the Higgs
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100
10
1
0.10
0.01
0.1 1 10 100CENTRAL ION TEMPERATURE, T (0) (keV)
Magnetic Fusion Pathways to Self-Heating
i
LA
WS
ON
PA
RA
ME
TE
R, n
(10
m
s)
it E20
-3
#97GR041.ntau-98 FIRE
D-T
D-D
Legend
JET
Q =1DT (Ignition)
TFTR
ALCC
JET
TFTRALCA
PLT
T10
DIII JT60
PLTTFR
TFR
T3
DIII-D
ATC
JET
JT-60U
JT-60U
Moderate Density Path
Higher Density Path
DIII-D
DIII-D
JETFT
ITER
Ignitor, CIT, FIRETFTR
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International Thermonuclear Experimental Reactor (ITER)
Pfusion ~ 1,500 MW for 1,000 seconds
Parties
US (left in 1998)
Japan
Europe
Russia
Cost ~ $10 B
Japan, Europe and Russia are continuing to work on a reduced size version with a goal of reducing the cost to ~$5B.
Demonstrate the scientific and technological feasibilityof fusion energy for peaceful purposes.
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Fusion Ignition Research Experiment(FIRE)
Design Features• R = 2.14 m, a = 0.595 m• B = 10 T• Wmag= 5.2 GJ• Ip = 7.7 MA• Paux ≤ 20 MW• Q ≈ 10, Pfusion ~ 150 MW• Burn Time ≈ 20 s• Tokamak Cost ≈ $375M (FY99)• Total Project Cost ≈ $1.2B
at Green Field site.
http://fire.pppl.gov
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1 1/2 -D Simulation* of Burn Control in FIRE
80
60
40
20
0
4 8 12 16 20 24 28 320
Alpha Power
Auxiliary Power
Ohmic Power
Time (seconds)
Power (MW)
BT(vac)
IP
BT(vac)
IP
10T, 6.44 MA, 21 s FT
Startup Burn Shutdown
Q = 11
Current RedistributionTime
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Concluding Remarks
• The capability now exists to produce and control fusion plasmasfor detailed investigation in the laboratory. However, fusionreactors based on the present state of knowledge are large andinnovations are needed for an attractive reactor concept.
• Recent developments in plasma diagnostics and computersimulation of three-dimensional non-linear phenomena now allowdetailed comparison of theory and experiment.
• New insight into the physical processes causing plasma transportcould lead to an advanced toroidal configuration that would have asignificant impact on the attractiveness of magnetic fusion.
• The FIRE compact high field tokamak could address many of the generic fusion science issues including: self-heated plasma physics, many of the long pulse advanced tokamak issues and couldbegin the study of self-heated self-organized plasmas in a $1B class experimental facility.
http://fire.pppl.gov
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Laboratories to Explore, Explain
VLBACHANDRA
HST CHANDRASNS
and Expand the Frontiers of Science
FIRENIF
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FIRE can help Solve the Mystery of Producing a Stationary Self-Sustained Fusion Fire.
CHANDRA
Crab Nebula
SOHO
VLBA
Galactic Jet - M87
Sun
FIRE
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Physics Requirements for Next Step Experiments
Study Physics of Fusion Plasmas (transport, pressure limits, etc.)
Same plasma physics if * = /a, = c/ b and are equal
Requires BR5/4 to be equal to that of a fusion plasma
Study Physics of Burning Plasmas (self heating, fast particle stability, etc)
Alpha heating dominant, f = P /Pheat = Q/(Q+5)
Q = function of n ET , e.g., Lawson diagram
n ET = B x function( *, ) is true in general
n ET = B x (BR5/4), if E is given by ITER98H empirical scaling at fixedbeta
Alpha particle confinement requires Ip(R/a) 9, Ip(R/a) ~ BR
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The Rosetta Stone for Fusion
Fusion Energy Fusion Science
plasma physics nτET ρ*, ν*, β (BR5/4)
burning physics Q = Pfus/Paux-heat fα = Pα/(Paux-heat + Pα)
time s, min, hr τE, τskin, etc
flexibility low high
availability high low
technology nuclear enabling
Fusion Science and Fusion Energy
have different languages, metrics, and missions.
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WAVE-PARTICLE INTERACTIONS ARE
CRITICAL FOR PLASMA SUSTAINMENT
• Plasma heating and current-drive- By beams of energetic neutral atoms- By radio-frequency waves
• Plasma self-heating by α particles
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nn
Neoclassical Theory Prediction ofSelf-Driven Plasma Current Confirmed*
TIME
• PLASMA SURFACE VOLTAGE IS WELL MODELED BY INCLUDING BEAM -DRIVEN AND SELF-DRIVEN (BOOTSTRAP ) CURRENTS.
• ENABLED DESIGN OF ADVANCED TOKAMAK , SPHERICAL TORUS, AND
STELLARATOR .
-0.5
0
0.5
1.0
Sur
face
Vol
tage
(V/tu
rn)
4.0 5.04.5
Measured
Ohmic onlyOhmic+NB
NBI
Ohmic+NB+Bootstrap