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Overview of Pilot Plant Studies and contributions to FNSTand contributions to FNST
Jon Menard,Rich Hawryluk, Hutch Neilson,Stewart Prager, Mike Zarnstorffg ,
Princeton Plasma Physics Laboratory
Fusion Nuclear Science and Technology Annual MeetingUCLA
August 2-4, 2010August 2 4, 2010
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Motivation for Pilot Plant studies
• Understand parameter space of FNS-capable facilities
– Provide context/choices for missions and designs of FNSF
– Identify remaining gaps necessary R&DIdentify remaining gaps, necessary R&D
– Is high neutron wall loading + small net electric possible?
• Assess requirements for net electricity from MFE
Required physics and technology performance design– Required physics and technology performance, design
– How large would pilot plant devices be?
• Have a plan to put electricity on the grid using MFE
– Demonstrate fusion’s viability and utility2
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FNSF-P Definition• FNSF-P = Fusion Nuclear Science Facility – Pilot
• A member of the FNSF family:
– Steady-state plasma operating scenariosSteady state plasma operating scenarios
– Neutron wall loading ≥ 1MW/m2
– Tritium self-sufficiency
Ultimatel capable of higher ne tron all loading for– Ultimately capable of higher neutron wall loading for component testing
Si d t b bl f d i h f i• Sized to be capable of producing enough fusion power for (small) net electricity - a “pilot plant”
• Assume S&T basis between ITER and ARIES3
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Key pilot metric is overall electrical efficiency Qeng
Qeng =ηth (MnPn + Pα + Paux + Ppump )
Paux + P + P b + P l + P lηaux
+ Ppump + Psub + Pcoils + Pcontrol
)/5/514( fuspumpnauxth PPQMQQ
ηη +++
η h = thermal conversion efficiency
)/1(5)(
fusextraaux
fuspumpnauxtheng PQP
QQQ
ηηη
+=
ηth thermal conversion efficiencyηaux = injected power wall plug efficiencyQ = fusion power / auxiliary powerMn = neutron energy multiplierBlanket and auxiliary heating n gy pPn = neutron power from fusionPα = alpha power from fusionPaux = injected power (heat + CD + control)Ppump = coolant pumping power
Blanket and auxiliary heating and current-drive efficiency + fusion gain largely determine electrical efficiency Q pump p p g p
Psub = subsystems powerPcoils = power lost in coils (Cu)Pcontrol = power used in plasma or plant control
that is not included in Pinj
electrical efficiency Qeng
Pumping, sub-systems power assumed to be proportional to inj
Pextra = Ppump + Psub + Pcoils + Pcontrolassumed to be proportional to Pthermal – needs further research
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ARIES and EU studies have explored range of technologies for blanket and divertor
Pl t t ffi i 0 31/0 33 0 35 0 37 0 42 0 60
• Higher temperature enables increased thermal efficiency
Plant net efficiency 0.31/0.33 0.35 0.37 0.42 0.60
– Plant net efficiency is defined as ratio between the net electrical power output and the fusion power 5
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FNSF-P study exploring 3 configurations:
• Advanced Tokamak (AT)– Most mature physics and technology data base
• Spherical Tokamak (ST)Spherical Tokamak (ST)– Most compact radially, vertical maintenance
• Compact Stellarator (CS)– Low re-circulating power, greatly reduced disruptivity
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Initial Qeng ≥ 1 design points identified for AT, ST, CS
• Thermal conversion efficiencies compared: ηth = 0.3 and 0.45AT d CS il t h f i 0 3 0 5GW ST i 2 hi h
Fixed ηaux = 0.4, Mn=1.1, AT/CS inboard shield + blanket thickness = 1m, ST inboard shield thickness = 15cm
– AT and CS pilots have fusion power = 0.3-0.5GW – ST is ~ 2× higher– ST pilot has highest neutron wall loading, smallest radial build– CS has highest Qeng due to small power for heating and current drive g
– Approximate, preliminary pilot size: 2/3 linear dimension of ARIES-AT, ST, CS
• Ongoing analysis priorities for FNSF-P size and availabilityOngoing analysis priorities for FNSF P size and availability– Blanket radial build, pumping power– Magnet current density
Maintenance schemes
• Technology advances offer the most benefit.
– Maintenance schemes– Divertor and first wall heat flux limits
7• What advances should be
assumed in the design?
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Advanced TokamakAdvanced TokamakFNSF-P Analyses
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AT size depends on achievable TF current density
ARIES TF coil algorithm allows about 45 MA/m2 average currentabout 45 MA/m average current density over the TF coil, while ITER design allows about 15 MA/m2
Variation of the allowed jTF from ARIES to ITER shows that larger major radii are required as the ITER
l i h dvalue is approached.
Using the ITER jTF the radial build of ITER b i t lITER can be approximately reproduced, when ITER operating point is input.
Working with MIT to develop a better understanding of what should be requirement for a pilot plant
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requirement for a pilot plant.
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Systems studies have identified additional important parameters that influence size and fusion power
4000
3500Shield Thickness = 1.25)
4000
3500 Fdiv rad = 0.70W])
3500
3000
2500
Shield Thickness = 1.00Shield Thickness = 0.75
P fus
= [M
W] 3500
3000
2500
Fdiv,rad 0.70Fdiv,rad = 0.80Fdiv,rad = 0.90
(Pfu
s =
[MW
2000
1500
n P
ower
(P
2000
1500
ion
Pow
er
1000
500
Fusi
on
2.0 3.0 4.0 5.0 6.0 7.0 8.0
1000
500
Fusi
Major Radius (R = [m])0 0
2.0 3.0 4.0 5.0 6.0 7.0 8.0
Major Radius (R = [m])
Increasing the allowable heat flux to the divertor or the radiated heat fraction increases the maximum
Inboard “shield thickness” is a consideration for the radial build
10
fraction increases the maximum fusion powers accessible.and affects machine size.
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Comparison of AT Pilot, ITER, ARIES
AT Pilot has smaller size higher field compared to ITER AT
11
AT Pilot has smaller size, higher field compared to ITER-ATNOTE: tradeoff between pilot plant thermal efficiency (0.3/0.45) and physics aggressiveness.Further work underway to benchmark pilot plant calculations vs. ITER, ARIES
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Spherical TokamakSpherical TokamakFNSF-P Analyses
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ST Pilot Plant study parameters, assumptions
Aspect ratio 1.7Plasma elongation 3.3Plasma triangularity 0.6Toroidal field at R0 2.4TE 0 5M VENBI 0.5MeVNon-inductive fraction 100% (BS+NBI)
• Scan major radius and density (Greenwald fraction)• Typically choose Pfusion, PNBI , QDT to be independent of ne
• Vary IP and H98 to achieve QENG=1, fNI=1
• Offset cost of increased R0 by reducing physics risk in QDT:• Choose ΔQDT º -5 for ΔR0 = +0.25m, q* > 2 limits maximum IP at low ne
• Solutions become more conservative as R0 is increased• Thermal conversion η=0 45 0 3 ΔIB hi ld=15cm SC PF coilsThermal conversion η 0.45, 0.3, ΔIB-shield 15cm, SC PF coils
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Increased ne / nG reduces H98, βN, fast ion fractionIncreased R0 reduces H98, βN, bootstrap fraction
But one disadvantage of increased density is increase in required fBS
14NOTE: R=2.25m* case is same as R=2.25m case but with PNBI = 40 60MW
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Now focusing on ST Pilots intermediate between ST-FNSF and ARIES-ST in size, β, fusion performance
15Possible ST progression: DD, PMI validate, FNS, component test, QENG 1
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Compact StellaratorCompact StellaratorFNSF-P Analyses
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Stellarator Pilot builds on ARIES-CS studyReference parameters for baseline:
NCSX lik 3 i dNCSX‐like: 3 periods
⟨R⟩ = 7.75 m
⟨a⟩ = 1 72 m⟨a⟩ = 1.72 m
⟨n⟩ = 4.0 x 1020 m–3
⟨T⟩ = 6.6 keV ⟨ ⟩
⟨B⟩axis = 5.7 T
⟨β⟩ = 6.4%
H(ISS04) = 1.1
Iplasma = 3.5 MA (b t t ) U Q i i t t t t k k lik fi t(bootstrap)
P(fusion) = 2.364 GW
P(electric) = 1 GW
• Use Quasi‐axisymmetry to get tokamak‐like confinement • 3D shaping for stability & sustainment
i h d i l d k kP(electric) = 1 GW
Ignited, no external heating• High density, low temperature compared to tokamaks• Only needs ~ “L‐mode” confinement
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High QEng > 1 accessible in stellarator pilot6
4
5
6
• External heating can be b t ti ll d d d t
2
3
B (
T) substantially reduced due to no-need for CD
0
1
3 4 5 6
Qeng=1.1Qeng=2Qeng=4
HISS04 < 2, βmax < 6%• Qeng=4.4 is maximum possible with assumed efficiencies: ηth=0.3, plant load is 7% of 3 4 5 6
Major Radius (m)
5
6
ηth , pthermal power
• All cases have Pdi < 10 MW / m2
3
4
B (
T)
Qeng = 1.1All cases have Pdiv < 10 MW / m
1
2
H-ISS04=2H-ISS04=1.5H ISS04 1 25
• Required confinement enhancement modest, sub‐H‐
d03 4 5 6
Major Radius (m)
H-ISS04=1.25 mode
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Neutron wall loading ≥ 1 MW/m2 for FNS testing possible in smaller major radius, higher Qeng CS Pilots
1 4
1.6m
2 )
p j , g Qeng
1.0
1.2
1.4Lo
ad (M
W/m • HISS04 < 2, βmax < 6%
0.6
0.8
utro
n W
all L
0.2
0.4
Peak
Neu
Qeng=1.1Qeng=2Qeng=4
0.03 4 5 6
Major Radius (m)
Qeng 4
• Higher wall loading possible at higher fusion power• Pfus = 475 MW, with HISS04 =2, β=6%, Pneut>2 MW/m2Pfus 475 MW, with HISS04 2, β 6%, Pneut>2 MW/m• R/<a> = 4.5m/1m, B0 = 5.7T 19
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Summary
• There is a range of FNSF missions, varying in their b fit d i kbenefits and risks.
• Net-electricity mission places high value onNet electricity mission places high value on technology advances to reduce device size and power consumption – useful for any FNSFpower consumption useful for any FNSF
• Push for smallest possible FNSF should be weighed i b fi f d i i iagainst benefits of modest increase in size:
– Increased physics margin (lower H98, βN, fBS, …)y g ( 98 βN BS )
– Increased space for magnets, blankets, divertors
Ability to access physics and technology closer to reactor– Ability to access physics and technology closer to reactor20