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New Horizons for Fusion – Advanced
Fuels for the 21st Century
New Horizons for Fusion – Advanced
Fuels for the 21st Century
G.L. Kulcinski
J.F. Santarius
G.L. Kulcinski
J.F. Santarius
Fusion Technology Institute
University of Wisconsin
Fusion Technology Institute
University of Wisconsin
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• Fusion fuels that emit few or no neutrons
• Not the DT or DD cycle (first generation)
• Most promising fuel cycle (second generation): D3He
• Future fusion fuel cycles-p11B, 3He3He (thirdgeneration)
What Do We Mean by Advanced Fuels?
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Key Fusion Reactions and the Formin Which the Energy is Released
1st Generation D + T �! n + 4He 17.6 MeV
D + D
% n + 3He 3.65 MeV
& p + T (ave.)
2nd Generation D + 3He �! p + 4He 18.4 MeV
3rd Generation p + 11B �! 3 4He 8.7 MeV
3He + 3He �! 2p + 4He 12.9 MeV
9=;
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10 -23
10 -22
10 -21
1 10 100
Ion Temperature (keV)
Rea
ctio
n R
ate
(m
3 /s)
50010 -22
Maxwellian Fusion Reaction Rates
D3HeD3He
3He3He3He3He
DTDT
p11Bp11BDDDD
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• FRC's
• Spheromaks
• High Power DensityTokamaks
• RFP's
• Inertial ElectrostaticDevices
• Colliding Beams
• ICF/DT "Spark-plug"
• Inertial ElectrostaticDevices
• Colliding Beams
Where Might We Economically Burn the Advanced Fuels?
• Inertial ElectrostaticDevices
• Colliding Beams
D3He p11B 3He3He, p6Li
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Reactivities (ΣEfus
σv) versus IEC Well Depth
10-23
10-22
10-21
10-20
10-19
1 10 100
IEF Well Depth (kV)
Rea
ctiv
ity
(MeV
-m
3 /s)
50010-24
DT
D3He
p-11B
3He-3HeDD
IEC Well Depth (kV)
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Inertial Electrostatic Confinement Devices Have
Already Been Operated With Non-DT Fuel
Inertial Electrostatic Confinement Devices Have
Already Been Operated With Non-DT Fuel
• Previous IEC devices produced steady state DD fusion plasmas
• Recent tests at the Univ. of Wisconsin with advanced fuels have
produced steady state D3He plasmas.
• Previous IEC devices produced steady state DD fusion plasmas
• Recent tests at the Univ. of Wisconsin with advanced fuels have
produced steady state D3He plasmas.
Illinois Inst. Tech. 5 x 107 n/s @ 150 kV
Univ. of Wisconsin 1 x 107 n/s @ 50 kV
Daimler-Benz 5 x 106 n/s @ 80 kV
Kyoto Univ. 5 x 106 n/s @ 55 kV
Univ. of Illinois 1 x 106 n/s @ 70 kV
INEL 3 x 105 n/s @ 40 kV
Illinois Inst. Tech. 5 x 107 n/s @ 150 kV
Univ. of Wisconsin 1 x 107 n/s @ 50 kV
Daimler-Benz 5 x 106 n/s @ 80 kV
Kyoto Univ. 5 x 106 n/s @ 55 kV
Univ. of Illinois 1 x 106 n/s @ 70 kV
INEL 3 x 105 n/s @ 40 kV
Preliminary Data > 106 p/s @ 45 kVPreliminary Data > 106 p/s @ 45 kV
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The Form of Energy Release is Quite Different in DT,DD, D3He and 3He-3He Fuel Cycles
The Form of Energy Release is Quite Different in DT,DD, D3He and 3He-3He Fuel Cycles
Apollo-L3Apollo-L3
Fractionof TotalEnergyReleased
Fractionof TotalEnergyReleased
ARIES-IARIES-I
DTDT D3HeD3HePOLYWELL™POLYWELL™
3He-3He3He-3He
00
2020
4040
6060
8080
100100
TransportTransport
TransportTransport
NeutronsNeutrons
BremsstrahlungBremsstrahlung
SynchrotronSynchrotron
SynchrotronSynchrotron
TransportTransport
BremsstrahlungBremsstrahlungBremsstrahlungBremsstrahlung
WILDCATWILDCAT
DDDD
NeutronsNeutrons
TransportTransport
NeutronsNeutrons
BremsstrahlungBremsstrahlung
SynchrotronSynchrotron
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0
50
100
150
200
250
300
350
400
450
500
Relative Amount of Fusion Reactions to
Make the Same Electrical Power
ARIES-I Wildcat APOLLO-L POLYWELL
The Amount and Form of Energy Required to Make Fusion Power is Quite Dependent on the Fusion Fuel Cycle
neutrons
transport
synchrotron
bremsstrahlung
DTD3He
DD
3He3He
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Major Advantages Major Disadvantages
• Significant reduction in radiation
damage (permanent first wall life)
• Greatly reduced radioactivity
(low level waste)
• Potential for direct conversion
(higher efficiency and lower waste
heat)
Why Consider the Advanced Fuels for Power Production?
• Higher operating "temperature"
(requires higher nτ values)
• Lower plasma power density or
yield (requires higher beta or ρr)
• Fuel source - 3He
(requires NASA collaboration)
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0
2 0 0
4 0 0
6 0 0
8 0 0
1000
1200
0 5 0 0 1000 1500 2000 2500 3000 3500
Maximum
Structural
Temperature,oC
Maximum dpa per 30 Full Power YearsMaximum dpa per 30 Full Power Years
TITAN (V)
ARIES-I (SiC)
UWMAK-I (AS)
ARIES-II (V)
STARFIRE (AS)
UWTOR-M (FS)
ASRA-6C (AS)
HSR (AS)
Apollo-L3Apollo-L3
Apollo-LApollo-L
ARIES-IIIARIES-III
ARIES-RS (V)
"Permanent"Life Regimefor Steel
The Low Radiation Damage in D3He Reactors AllowsPermanent First Walls to be Designed
ARIES-IV (SiC)
UWMAK-II (AS)
UWMAK-III (Mo)
NUWMAK (Ti)
WITAMIR-I (FS)
MINIMARS (FS)
ARIES-ST (FS)
MARS (FS)
DT FuelD3He Fuel
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Class of Relative LWR Fission DT D3He p11BWaste Cost of (Once Through) (SiC) (SiC) 3He3He,
Disposal p6Li
Class A 1
Class C ≈10
Deep ≈1000Geological(Yucca Mtn.)
The Use of 2nd and 3rd Generation Fusion Fuels Can GreatlyReduce or Even Eliminate Radioactive Waste Storage Problems
Relative Volume of Operation Waste/GWe-y
5555
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FUS
ION
• TECHNOLOGY • IN
ST
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•
W I S C O NS IN
•
APS-DPP 1998
1. � 1019 5.� 10191.� 1020 5. � 10201. � 1021 5. � 10211. � 1022
nt Hm-3sL
1
5
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50
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500
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iT
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1. � 1019 5.� 10191.� 1020 5. � 10201. � 1021 5. � 1021
1
5
10
50
100
500
1000
D-T
3He:D=1:1
D-3He Fuel Requires High b, nt, and T
2 5 10 20 50 100Ion temperature HkeVL
0.001
0.005
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0.5
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evitaleR
noisufre
wopytisned
1 2 5 10 20 50
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0.5
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D-T
3He:D=1:1
D-D
• Power density in the plasmamust be increased to take ad-vantage of b2B4 scaling.
• T and nt must each be 4 to 5times higher for D-3He com-pared to D-T
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FUS
ION
• TECHNOLOGY • IN
ST
I TU
TE
•
W I S C O NS IN
•
APS-DPP 1998
n Fusion power density scales as b2 B4.
n Superconducting magnets can reach 20 T.
n Potential power-density improvement by increasing B-field tolimits is ~2000!
D-3He, Unlike D-T, Fuel Could Use the High PowerDensity Capability of Innovative Fusion Concepts
• Promising high-power-density concepts are under investigation;e.g., FRC, spheromak, ST, RFP, IEC.
• D-T fueled innovative concepts become limited by first-wallneutron or surface heat loads well before they reach b or B-fieldlimits.
• D-T fueled, high-b innovative concepts optimze at B~3 T.
• D-3He needs a factor of ~ 80 above D-T fusion power densities.
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FUS
ION
• TECHNOLOGY • IN
ST
I TU
TE
•
W I S C O NS IN
•
APS-DPP 1998
D-3He Fuel Allows High-Power-DensityInnovative Concepts to Use Their Full Capabilities
D-TTokamak
D-TFRC
D-3HeFRC
Beta 0.05 0.67 0.67
Magnetic field on coil, T 18 2.3 8.2
First-wall radius, m 1.4 2 1.5
2pR0 or Length, m 36 25 20
Fusion power, MW 2000 2000 2000
Neutron wall load, MW/m25 5 0.2
Surface heat load, MW/m21.3 0.09 2.9
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• Helium-3 concentrationverified from Apollo 11, 12,14, 15, 16, 17 and U.S.S.R.Luna 16, 20 samples.
• Current analyses indicatethat there are at least1,000,000 tonnes of helium-3imbedded in the lunarsurface.
• Helium-3 concentrationverified from Apollo 11, 12,14, 15, 16, 17 and U.S.S.R.Luna 16, 20 samples.
• Current analyses indicatethat there are at least1,000,000 tonnes of helium-3imbedded in the lunarsurface.
Lunar Helium-3 Is
Well Documented
Lunar Helium-3 Is
Well Documented
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% Titanium Dioxide2 4 6 8 10 12
10
20
30
40
50
AvAv
AvAv
He
Co
nte
nt
– w
pp
m
Mare Regolith
Highland Regolith
The Association of Helium with Ti in the Lunar Regolith
Enables Us to Pick the First Potential Mining Site
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Physics Easiest Harder Hardest
(10 keV) (50 keV) (≥ 200 keV)
First Wall Life 3–4 FPY's Full Lifetime Full Lifetime
(Matls. Dev. Prog.) (extensive) (small) (off-the-shelf)
Radioactivity (vs. Fission)
after 1 day ≈ same 3% 'None'
after 100 years 0.1% 0.003% 'None'
Electrical Efficiency ≈ same 1.5–2 times ≈ 1–1.5 times
(vs. fission) higher higher
Key Technological Features of Fusion Fuels
1st Generation 2nd Generation 3rd Generation DT D3He 3He3He, p11B
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1) eliminating one of the greatest barriers to public acceptance
of nuclear power – the concern over radioactive waste and
radioactivity releases
2) allowing off-the-shelf structural materials to be used, thus
eliminating expensive neutron test facilities & long
development times
3) eliminating T2 breeding blankets and complicated secondary
coolant loops
4) allowing high efficiency operation and inter-city siting of
electrical power plants
Conclusions
The use of advanced fusion fuels could revolutionize the Public's
view of fusion power by:
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• These compelling attractive features can only be
achieved by a vigorous research program on
magnetic, inertial electrostatic, and/or inertial
fusion concepts specifically suitable for the burning
of advanced fusion fuels.
• One of the metrics used to determine the
attractiveness of fusion confinement concepts
should be the ability to burn the advanced fusion
fuels.
Recommendations