Chapter 1. Introduction Magnetic Fusion Technology Thomas J Dolan - - PowerPoint PPT Presentation

Chapter 1. Introduction Magnetic Fusion Technology

Thomas J Dolan Thomas J. Dolan NPRE 421 University of Illinois 2011 2011

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Some Forms of Energy

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Some Forms of Energy

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Energy usage in the USA Industrial 41 % Transportation 25 % Transportation 25 % Residential 19 % Commercial 14 %

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Energy to agriculture and manufacturing Energy to agriculture and manufacturing

~ 8 Joules (tractor, chemicals, transportation)  One Joule of food Processing energy costs are > 30% of following product costs: Processing energy costs are > 30% of following product costs:

• steel
• aluminum

l

• glass
• cement
• paper.

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GDP vs. Energy Cosumption

60

103 $/cap

40 50 30 40 10 20 2 4 6 8 10 12

kW/

AG = Argentina, AL = Australia, AU = Austria, BR = Brazil, CA = Canada, CH = China, CZ = Czech, DE = Germany, FR = France, GR = Greece, HU = Hungary, ID = Indonesia, IN = India, .IR = Iran, IT = Italy, JA = Japan, MX = Mexico, NO = Norway, PK = Pakistan, RU = Russia, SA = South Africa,

kW/cap

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SP = Spain, SW = Sweden, SZ = Switzerland, TU = Turkey, UK = United Kingdom, US = USA.

International Energy Outlook 20 25

• n, TW

15 20 sumptio 20 TW 10 15 gy Con 5 Energ 1980 1990 2000 2010 2020 2030 Year

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World energy resources World energy resources

Power Limits, TW Renewable Energy Resources Current Ultimately Solar 13.5 1580 Biomass 1.74 8.56 Wind 0 09 130 Wind 0.09 130 Wave and Tidal 0.05 1-10 Hydro 0.75 11 y Geothermal 0.01 0.3 Organic Waste 0.02 0.1

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World energy resources World energy resources

E Li it Energy Limits Recoverable Fossil Fuels Joule TW-years Coal and Lignite (9.09E11 ton) 2.4x1022 753 Crude Oil (1.34E12 barrels) 7.9x1021 249 Natural Gas (1.7E14 m^3) 6.6x1021 208 Tar Sand Oil (3 7E12 barrels) 2 2x1012 703 Tar-Sand Oil (3.7E12 barrels) 2.2x1012 703 Shale Oil (3.33E12 barrels) 1.9x1022 613

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World energy resources World energy resources

Nuclear Fission Fuels Joule * TW-years U-235 (3 88E4 tonnes) 2 5x1021 95 U-235 (3.88E4 tonnes) 2.5x10 95 U-238 (5.43E6 tonnes) 3.5x1023 13000 Th-232 (2.57E6 tonnes) 1.7x1023 6300 Nuclear Fusion Fuels Joule TW-years Nuclear Fusion Fuels Joule TW years Lithium in ocean (2.3E14 tonnes) 1.4*1031 4.2*10^11 Lithium on land (2 84E7 tonnes) 1 7*1024 5 2*10^4 Lithium on land (2.84E7 tonnes) 1.7*1024 5.2*10^4 Deuterium (5.17E13 tonnes) 1.6*1031 5.1*10^11

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Why develop fusion reactors? Why develop fusion reactors?

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Fusion reactions power the sun and other stars and other stars

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World energy flows, TW

Mankind uses ~ 20 TW

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Mass per nucleon vs. atomic number

E = Mc2 E Mc

Fe

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Why develop fusion reactors?

Deuterium & lithium are

• Abundant
• Cheap

1 L(H2O) = 300 L(gasoline)

• Cheap
• Available to all nations.

Safe – no supercriticality or meltdown hazard Materials No fission fragments or actinides No high level radioactive waste g (but much low level radioactivity) Recycling of tritium, lithium and vanadium Fusion could help reduce Fusion could help reduce pollution competition for fossil fuels th t f

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threat of war

Temperature units

T K kT J k = 1.381x10-23 J/K kT/e eV e = 1 602x10-19 C kT/e eV e = 1.602x10 C It is common to speak of T in units of k V keV. 1 eV = 11605 K 1 keV = 11.605 MK

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Energy released by fusion reactions D+T  4He(3.52) + n(14.1) 17.59 MeV

3

D+D  3He(0.82) + n(2.45) 3.27 MeV D+D  T(1.01) + H(3.02) 4.03 MeV ( ) ( ) D+3He  4He(3.66) + H(14.6) 18.3 MeV T+T  n + n + 4He 11.3 MeV H

6Li  4H 3H

4 02 M V H+6Li  4He + 3He 4.02 MeV H+11B  4He + 4He + 4He 8.68 MeV

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Example Problem p

How many deuterium atoms are there in one liter of water, and how much energy could they produce in a l d DD (7 2 M /d )? catalyzed DD reactor (7.2 Mev/deuteron)?

N(water) = Nav/M = (1000 g/liter) (6.02x1023 molecules/mole) / (18 g/mole) = 3.34x1025 molecules/liter. 3.34x10 molecules/liter.

Deuterium ~ 1.53x10-4 of hydrogen atoms.

N(deuterium) = 2 (3.34x1025) 1.53x10‐4 = 1.02x1022 atoms The energy released is W = 1.02x1022 (7.2 MeV) 1.60x10‐13 J/MeV = 1.18x1010 J = 11.8 GJ.

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Main reactions for breeding tritium fuel

6Li + n(thermal)  4He(2.05) + T(2.73) 4.78 MeV 7Li + n(fast)  4He + T + n

• 2 47 MeV

Li + n(fast)  He + T + n 2.47 MeV endothermic N t l lithi 7 42% 6Li d 92 58% 7Li Natural lithium = 7.42% 6Li and 92.58% 7Li

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Catalyzed DD fuel cycle Catalyzed DD fuel cycle

D+D  3He(0 82) + n(2 45) D+D  3He(0.82) + n(2.45) D + 3He  4He(3.66) + p(14.6) D+D  T(1.01) + p(3.02) D+T  4He(3.54) + n(14.05) _____________________________ Net: 6D  2n + 2p + 2(4He) + 43.2 MeV

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H + 6Li and H + llB reactions H Li and H B reactions

no neutron emission no neutron emission all reaction products are charged particles direct conversion to electricity but but low power densities and cross sections very high temperature operation Ignition difficult or impossible

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Approximate Fuel Costs, 2009 $/GJ

Fossil Fuels Fossil Fuels

Crude Oil 10.18 OPEC Natural Gas 5.19 EIA Macquarie Group Coal Limited Thermal 2.6 Coke 3.82

Fission Fuels

Uranium Ux Consulting Company Uranium Company U-235 0.2 U-238 0.0014 Los Alamos Thorium 0.066 National Laboratory Fusion Fuels Deuterium 0 15 Sigma-Aldrich Corporation

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Deuterium 0.15 Corporation Lithium 0.038 Sigma-Aldrich Corporation

Fusion advantages over fission Fusion advantages over fission

* No supercriticality hazard * no emergency core cooling systems * no fission products or long lived high level radioactive waste * no fission products or long‐lived high‐level radioactive waste (there would still be lower‐level radioactive wastes) * possible recycling of materials (such as V‐Cr‐Ti alloy) possible recycling of materials (such as V Cr Ti alloy) * widespread availability and easy transport of fuels * low cost of fuels.

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How can we make a fusion reactor? How can we make a fusion reactor?

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Fusion Power Plant

Magnetic fusion reactor power plant

blanket

turbine

shield

steam generator

IHX

magnet

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Need for Heating

T = 10 keV (120 Million Kelvin). positive fuel ions repel each other hi h l iti  h l f ti t high velocities  approach close for reactions to occur. fuel becomes “plasma” = fully ionized gas, stars fluorescent lights welding arcs welding arcs flames ionosphere i d t i l l i d i industrial plasma processing devices gaseous lasers nuclear fusion experiments

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Plasma requirements for a fusion reactor

Heating T > 10 keV to overcome Coulomb repulsion Confinement n > 1020 m-3s “Lawson Criterion” Magnetic confinement n ~ 1020 m-3  ~ 1 s Inertial confinement Inertial confinement n ~ 1029 m-3  ~ 1 ns

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Confinement

Long enough for a few percent of the fuel to “burn” Long enough for a few percent of the fuel to burn . * solid walls. Low‐temperature plasmas, such as fluorescent lights. * gravity. Stars * inertia. Laser beams  fuel pellet  extremely high density. Inertia limits expansion rate for times ~ 1 ns. * electrostatic fields. Spherical High voltage grids * magnetic fields. Lorentz force F =  electrons and ions spiral around B field lines. * electromagnetic waves. Radiofrequency waves and microwaves

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Toroidal magnetic field Toroidal magnetic field

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Plasma energy loss mechanisms

Plasma flow along B – open magnetic systems Plasma Drift across B, caused by E, B, magnetic field curvature, … Heat Transport – conduction and convection Radiation Losses– line radiation and bremsstrahlung radiation ad at o

• sses

e ad at o a d b e sst a u g ad at o Magnetohydrodynamic (MHD) instabilities (plasma shape) driven by gradients of pressure or current density Microinstabilities – interactions of particles and waves Charge exchange (neutralization of hot ions allowing their escape) Charge exchange (neutralization of hot ions, allowing their escape)

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Plasma Heating Methods

Ohmic Compression Charged particle injection Alpha particle heating Alpha particle heating Neutral beam injection Radiowave and microwave heating

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Plasma beta Plasma beta

 = (plasma pressure)/(magnetic field pressure)  (p p )/( g p )  = p/(B2/2o) If B = 1 Tesla, then

2/

B2/2o = 0.4 MPa = 4 atmospheres

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Energy gain ratio Q Energy gain ratio Q

Q = (fusion power) / (input power) Q ( p ) / ( p p ) Q ≈ 5(nT) / [ 5x1021 - nT ] n = fuel ion density, m-3 T = ion temperature, keV fi t ti  = energy confinement time, s

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Energy gain ratio vs. triple product

1000

Q

100 10 1 0.1 1 2 3 4 5

nTt 1021 m-3keV s

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nTt , 1021 m-3keV-s

Typical values for triple product Typical values for triple product

* magnetic confinement fusion: g n ~ 1020 m‐3, T ~ 10 keV, ~ 1 s. * inertial confinement fusion: inertial confinement fusion: n ~ 1029 m‐3, T ~ 10 keV, ~ 1 ns.

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Reaction Rate with Two Maxwellian Distributions

r(x,t) = n1(x,t) n2(x,t) <v>

If nD = nT = ½ n, then r = ¼ n2 <v> r = ¼ n2 <v>DT

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Interactions among like particles

N = n(n-1)/2 ≈ n2/2 if n>>1 For DD reactions r = (½)n2 <v>

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For DD reactions r = (½)n2 <v>

Fusion Power Density

nD = nT = ½ n PDT = (¼) n2<v>WDT PDD = Pf = (½)n2[<v>ddnWddn + <v>ddpWddp] ≈ (½) n2<v>ddWdd ( )

dd dd

Pcat ≈ (½) n2<v>ddWcat The factor of ½ avoids counting the same DD reaction twice.

Catalyzed DD fuel cycle

D+D  3He(0.82) + n(2.45) D

3H

 4H (3 66) (14 6) D + 3He  4He(3.66) + p(14.6) D+D  T(1.01) + p(3.02) D+T  4He(3.54) + n(14.05) _____________________________ Net: 6D  2n + 2p + 2(4He) + 43.2 MeV Each DD reaction results in consumption of 3 deuterons, yielding 21.6 MeV = 3.46x10‐12 J.

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Reaction rate Parameters <v> 1 D+T

• 1. D+T
• 2. D+3He
• 3. D+DH+T

4 T T

• 4. T+T
• 5. T+3He
• 6. H+11B

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Reaction Rate Parameters Reaction Rate Parameters

T keV <v> m3/s <v> m3/s T, keV <v>DT, m /s <v>DD, m /s 8 5.94E-23 6.90E-25 10 1.09E-22 1.21E-24 15 2.65E-22 2.97E-24 20 4.24E-22 5.16E-24 25 5.59E-22 7.60E-24 30 6.65E-22 1.02E-23

Fusion Power Density

Example: n=2x1020 m-3, T = 10 keV PDT = (¼) n2<v>WDT

DT DT

PDT = ¼ (1040 ) 1.09x10-22 2.82x10-12 = 7 2x105 W/m3 = 0 72 MW/m3 7.2x10 W/m 0.72 MW/m PDD = (½)n2[<v>ddnWddn + <v>ddpWddp]

0 5 1040 [ 0 626 10 24 5 24 10 13 0 582 10 24 6 46 10 13 ]

= 0.5x1040 [ 0.626x10-24 5.24x10-13 + 0.582x10-24 6.46x10-13 ] = 0.0035 MW/m3 Pcat ≈ (½)n2<v>ddWcat = (½)1040 1.21x10-24 3.46x10-12 = 0.021 MW/m3

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Plasma Pressure

p = sum of pressures of (fuel ions + electrons + impurity ions) p = niTi + neTe + nzTz If n = 0 and Ti ≈ T = T then If nz 0 and Ti ≈ Te T, then p ≈ 2nT Example: n = 1020 m-3, T = 10 keV p ≈ 2x1020 m-3 10 keV 1.602x10-16 J/keV = 3.2x105 Pa = 0.32 atm

Optimum Temperature

p = 2nT  n = p/2T p = 2nT  n = p/2T PDT = (¼) n2<v>WDT = (¼) (p/2T)2<v>WDT At a given pressure what T maximizes P ? At a given pressure, what T maximizes PDT ?

T, keV <v> (10-22 m3/s) <v>/T2 5 0.129 0.0052 5 0.129 0.0052 8 0.594 0.0093 10 1.09 0.0109 15 2.65 0.0118 20 4.24 0.0106 25 5 59 0 0089 25 5.59 0.0089 30 6.65 0.0074 35 7.45 0.0061 40 8.03 0.0050

Reactor Power Balance Reactor Power Balance

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Toroidal coordinate system Toroidal coordinate system

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Definitions of a, b, c Definitions of a, b, c

minimize Vbsc = 2Ro  [(a+b+c)2 – a2]

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Estimation of required b, c Estimation of required b, c

Tritium breeding ratio > 1 and C il hi ldi f 10 6  b 1 2 Coil shielding factor 10‐6  b ~ 1.2 m magnet coil stress < 300 MPa, and coil volume minimized  c ≈ 0 25(a+b) coil volume minimized  c ≈ 0.25(a+b) (Freidberg, 2007)

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Optimization of R, a

V = 2Roa2 S = 2Ro2a Neutron wall power flux: P 0 8 (fusion power density)V/S < 4 MW/m2 Pw = 0.8 (fusion power density)V/S < 4 MW/m2 Electrical power PE = 1.2 e (fusion power density)V PE 1.2 e (fusion power density)V Vbc/PE = 2Ro  [(a+b+c)2 – a2] / (3SPw e /2) Minimizing this ratio  a = (5/3)b = 2.0 m, c = (a+b)/4 = 0.8 m If Pw = 4 MW/m2, and PE = 1000 MWe, then R o = 0.04 PE/aPw ≈ 5 m

(Freidberg, 2007)

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Determination of reactor parameters Determination of reactor parameters

Nuclear cross sections  b ~ 1.2 m B and stress limit  c (a+b)/4 Bmax and stress limit  c (a+b)/4 Cost optimization  a 2 m Electrical power & neutron wall loading  Ro 5 m Fusion power & volume  p Fusion power & volume  p Maximization of fusion power density  optimum T High‐Q or ignition  required value of  Plasma pressure and B  required value of  

(Freidberg, 2007)

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What Experiments Are Underway?

http://www.iterbelgium.be/en/system/files/upload/n___Fusion_research_in_Belgium_‐_R__Weynants.pdf

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Joint European Tokamak (JET)

Culham Laboratory UK U

Tokamak Fusion Test Reactor (TFTR)

Large tokamaks

D III-D JT-60 JET Location Location R m 1.66 3.4 2.96 a m 0.67 1 0.96 B T 2 2 4 2 4 B, T 2.2 4.2 4 current I, MA 3 5 6 ECH, MW 6 4

• ICH, MW

5 10 12 NBI, MW 20 40 24 LH MW

• 8

7 LH, MW 8 7 Achievements  > 12% long pulses ~ 28 s equivalent Q > 1. b i d d P(DT) = 15 MW B ll

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being upgraded Be walls

Plasma Shapes

R/a = “Aspect Ratio” R/a Aspect Ratio

a R a R

Ordinary Tokamak Spherical Tokamak Compact Stellarator Tokamak R/a ~ 4 Tokamak R/a ~ 1.4 Stellarator R/a ~ 6

MegAmpere Spherical Tokamak (MAST)

• -------

R = 0.85 m

National Spherical Torus Experiment (NSTX) (NSTX)

 = (plasma pressure) / (magnetic field pressure) ~ 0.3

Simulation of IRE in ST

National Institute of Fusion Science, Japan Growth of helical perturbation

Globus-M

a=0 24 m

Globus M

a 0.24 m R=0.37 m Bt = 0.35 T I 0 25 MA Ioffe Institute, St. Petersburg, Russia I = 0.25 MA (future 0.5 MA) V = 4V



Pulse ~ 60 ms (future 200 ms)

Experimento Tokamak Esférico (ETE)

Brazilian National Space Science Institute, INPE

Assembly

• f SUNIST

Website “All the world’s tokamaks” http://www toodlepip com/tokamak/ http://www.toodlepip.com/tokamak/

Stellarators Stellarators

Conventional stellarator torsatron or heliotron Conventional stellarator torsatron or heliotron

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LHD coils LHD coils

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LHD helical coils LHD helical coils

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L H li l Large Helical Device, Toki, Japan

Wendelstein 7‐X coils Wendelstein 7 X coils

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W7X Stellarator

W7X Modular Coil

Large stellarators

LHD Japan W 7-X Germany LHD, Japan W 7 X, Germany Location R, m 3.5-3.9 5.5 , a, m 0.6 0.53 B, T 2 - 3 3 number of helical coils 2 50 modular coils ECH MW 2 10 ECH, MW 2 10 NBI, MW 15 5 ICRH MW 3 3 ICRH, MW 3 3 pulse length, s > 103 s at low n 1800 nT m-3keV-s 4 4x1019 under construction

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nT m keV-s 4.4x10 under construction

National Compact Stellarator Experiment (NCSX)

Potential advantages of stellarators

• ver tokamaks

No disruptions Current free operation  slower heat loss Current free operation  slower heat loss Plasma current drive not required  lower input power, higher Q

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Alternative confinement concepts

Reversed field pinches (RFP) spheromaks spheromaks field reversed configurations (RFC) magnetized target fusion (MTF) tandem mirrors rotating plasmas rotating plasmas internal rings

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Alternative Concepts

Reversed Field Pinch (RFP)

“Taylor Minimum Energy State” oJ = xB = kB Dynamo turbulence adjusts magnetic field components.

Spheromaks

• 1. Magnetic field
• 2. Puff hydrogen
• 3. Apply high voltage

V

• 5. Plasma expansion
• 6. Sustained spheromak
• 4. Plasma acceleration

Sustained Spheromak Physics Experiment (SSPX) p y p ( ) a ~ 0.22 m,  ~ 5%, B ~ 0.25 T, T

e ~ 200 eV for several ms.

Field Reversed Configurations (FRC)

Separation Coils Fluxcores p F Coils EF Coils .19m m

Coaxial Gun

1.8m .19m

Coaxial Gun

1.8m OH Coil Torus Coils

TS-4 U of Tokyo: R ~ 0 5 m R/a ~ 1 2-1 9 B ~ 0 4 T I ~ 300 kA.

• Y. Ono, U. of Tokyo

TS 4, U. of Tokyo: R 0.5 m, R/a 1.2 1.9, B 0.4 T, I 300 kA.

Merging Two Spheromaks t F FRC to Form an FRC

• Y. Ono, U. of Tokyo

, y

Repetitively Merging Spheromaks

Plasma Core Plasma Sheath Shield Plug Over Vacuum Pumps Vacuum Pump (4 total) (Ceramic Rotors) Feedback Coils CT Formation & Push Coils Central Core Plasma Sheath 1.2 m Blanket Separatrix with Pumping Coaxial Accel. S/C Coil (8 total) Inductive Accel. Region Vacuum Pump (2 total) T i t d First Wall Tubes

5

Hollow Twisted Divertor Plates and Structure C-X Neutrals Pumping Channel Section Away From Pumps

meters

• R. BOURQUE

SPHACTIV 12/98

Conducting Core

Magnetized Target Fusion (MTF) Plasma

Achieved n < 8x1016 cm-3, T ~ 300 eV, B ~ 3 T,  ~ 10 s.

• J. M. Tacetti et al., RSI 74 (2003) 4314-4232.



Magnetized Target Fusion (MTF)

W = 5 MJ

Magnetized Target Fusion (MTF)

Magnetic Mirrors

Inertial Confinement Fusion (ICF)

Compression Methods

National Ignition Facility – 192 beams

Plasma around Target Sphere

High Gain ICF Targets

F DT f l Frozen DT fuel can be compressed to very high density. y g y TaCHO pusher stops x-rays and stops x rays and hot electrons to prevent preheating fuel.

NIF Target Chamber Interior

Laser MegaJoule (LMJ), France

240 beams, 1.8 MJ, 600 TW operation 2010

Osaka University Laser Room Osaka University Laser Room

ICF Problems

ICF Problems

Diode‐Pumped Solid State Lasers (DPSSL)

Cooled by He gas flowing at Mach 0.1

Diode‐Pumped Solid State Lasers (DPSSL)

M L Yb S FAP l b  20 J l Mercury Laser: Yb:S-FAP slabs  20 J per pulse Goal: 100 J 10 ns 10 Hz 10% efficiency Goal: 100 J, 10 ns, 10 Hz, 10% efficiency

Electra KrF Laser, NRL

L lif l t b th d d f il Long-life electron beam cathode and foil Laser gas cooling system, long-life windos > 500 J in 100 ns pulses, scalable to higher energy

Potential Advantages of Heavy Ion Fusion

Beam coupling to target Att i bl d t Attainable energy and current High repetition rates Efficiency > 20% y Issues Beam charge neutralization & focusing Beam charge neutralization & focusing Accelerator cost

What has been accomplished? What has been accomplished?

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Plasma research progress

1920s Langmuir ‐‐ gas discharges “plasma” 1930s Bennet – pinch equilbrium equation Landau – collisionless damping of waves Landau – collisionless damping of waves 1940s Thomson ‐‐ patent of fusion reactor scheme 1950s Lavrentyev ‐‐ proposed electrostatic confinement in USSR Tamm & Sakharov – magnetic confinement Tamm & Sakharov magnetic confinement England & USA – early experiments 1958 Geneva Conference on Peaceful Uses of Atomic Energy many experiments were failing 1960s Ioffe ‐‐ stabilization with minimum‐B field 1968 Artsimovich ‐‐ IAEA conference T‐3 results 1970s Many tokamaks built. A few stellarators continued Success in tandem mirrors.

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Research Progress

1980s Good results from large tokamaks. Cancellation of Mirror Fusion Test Facility in USA Discovery of H-Mode in ASDEX (Germany). 1990s Strong plasma theory Excellent 3-D plasma simulations Cancellation of Tokamak Fusion Test Reactor in USA Fusion power plant design studies Design of International Thermonuclear Experimental Reactor (ITER) by Europe, Japan, Russia, USA 2000s Siting of ITER in France New ITER members China, Korea, India Beginning of ITER construction C Large ICF experiments under construction Good results from Large Helical Device in Japan W7-X under construction in Germany Cancellation of National Compact Stellarator Experiment in USA Cancellation of National Compact Stellarator Experiment in USA

Triple Product vs. Year

1022 1021

20

nT m-3keV•s

1020 1019 1018 1018 1017 1016 10 1015 1014 1013

1960 1970 1980 1990 2020

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Fusion triple product compared with semiconductors and accelerators and accelerators

ITER

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Year

What are the future plans? What are the future plans?

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Fusion Power Plants

I ti l f i (l i b ) i iti i 2011 Inertial fusion (lasers or ion beams) – ignition in 2011 laser efficiency and cost chamber pulse repetition rate p p Tokamaks & Stellarators ~ 10 MWth produced in USA & UK 10 MWth produced in USA & UK ITER project  400 MWth, 400 s 2026 C t t id ll d l d Compact toroids – smaller, undeveloped Neutron source for materials testing Development ~ 100 G$ needed. (= 2 months US military)

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World < 2 G$/y

International Thermonuclear Experimental R (ITER) Reactor (ITER)

1985 Mitterand, Gorbachev, Reagan ‐‐ International collaboration 1988‐1992 ITER Conceptual Design Activity, Europe, Japan, Russia, USA 1992‐1998 ITER Engineering Design Activity at 3 sites: Japan, Germany, USA p , y, 1998 Shortage of funds. Request for redesign to cut costs. US quits. 2003‐2005 US rejoins. China, Korea, India join.

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2005‐2007 negotiations on siting in France or Japan.

Reduction of ITER parameters Reduction of ITER parameters

Ignition 1998 “High‐Q” 2005 Q ∞ (Ignition) 10 Pf, MW 1500 400 Pf, MW 1500 400 Burn, s 1000 400 R/a, m 8.1 / 2.8 6.2 / 2.0 I MA 21 15 I, MA 21 15 Bf, T 5.7 5.3 # TF coils 20 18  ripple problem

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ITER cross section

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TF coil central solenoid blanket modules access port plug access port plug divertor cryopump person

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ITER operation phases ITER operation phases

H Phase – studies of plasma control, stability, transport, heat flux divertor runaway electrons electromagnetic loads heat flux, divertor, runaway electrons, electromagnetic loads, diagnostics, etc. D Phase – deuterium operations, nuclear reactions, small amounts of tritium, shielding performance. DT Phase – full fusion power operation, tritium control, non‐inductive, steady‐state current drive, long‐term burn, blanket module testing high heat flux and neutron fluence testing blanket module testing, high‐heat‐flux and neutron fluence testing.

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Japanese fusion power plant design

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Strong Economy of Scale Available

12 13 COE, Yen/kWh

beta = 2%

10 11 12

Hiss = 2 1.7

7 8 9

3% 4%

1.5

5 6 7

4% 5%

4 5 0.5 1 1.5 2 2.5 3 3.5 P GW Pe, GWe

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ICF Chamber Protection

Lithium or Pb-Li streams (dashed lines) protect the walls from blast damage and absorb neutrons damage and absorb neutrons to breed tritium. The liquid metal is collected in a pool at the bottom and pumped back to the top. p “High Yield Lithium Injection Fusion Energy (HYLIFE)” Energy (HYLIFE) .

Conclusions

Fusion energy – safe, environmentally friendly Enormous potential : 1 liter water = 300 liters gasoline Very difficult : T ~ 100 million K Require nTt > 3x1021 m-3 KeV s Require nTt 3x10 m KeV s NIF ignition in 2011, but efficiency and repetition rate problem ITER should demonstrate 400 MW for 400 s in 2026 ITER should demonstrate 400 MW for 400 s in 2026 Next step = demonstration power plant ~ 100 G$ needed to develop fusion energy World spending ~ 2 G$/year

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Fusion energy  cost competitive if:

• High fossil fuel prices
• Difficulty with coal transportation and waste
• Tax on carbon emissions
• Novel fusion reactor successful (spheromak, …)
• e us o

eacto success u (sp e o a , )

• Economy of scale utilized (1 3 GWe)
• Fusion fission hybrids deployed
• Fusion-fission hybrids deployed
• Difficulty siting fission power plants (protests, …)

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The Nuclear Industry Faces Protests

“W ’ h t i t t “We’re here to sing our protest songs. Plug this in for me, will you, fella?”

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She may look like somebody’s granny to you, y y g y y , but she was instrumental in putting a $4-billion nuclear power plant in the deep freeze.

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Extra Slides

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