Topics to be Discussed

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Topics to be Discussed

• Vision for Magnetic Fusion Power Plant
• Conventional Mode Operation in FIRE
• Advanced Mode Operation in FIRE
• O-D Systems analysis
• 1.5-D Tokamak Code Simulation
• RWM Stabilization Concept
• Issues Needing RD
• Concluding Remarks

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ARIES Economic Studies have Defined the Plasma
Requirements for an Attractive Fusion Power Plant
Plasma Exhaust Pheat/Rx 100MW/m Helium
Pumping Tritium Retention
High Power Gain Q 25 - 50 ntET 6x1021
m-3skeV Pa/Pheat fa 90
Plasma Control Fueling Current Drive RWM
Stabilization
High Power Density 6 MW-3 10 atm
Steady-State 90 Bootstrap
Significant advances are needed in each area. In
addition, the plasma phenomena are non-linearly
coupled.
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W7-AS
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Attractive Reactor Regime is a Big Step
From Today
Modification of JT60-SC Figure
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Fusion Development Considerations for FIRE
Address key physics issues for an advanced
reactor burning plasma scenarios similar to
ARIES controlled burn of high power density
plasma with Q gt5, fBS 80 Focus technology
on areas coupled to the plasma high power
density plasmas plasma facing
components plasma control technologies
Limit scope/size of the device size
comparable to todays largest tokamaks to reduce
cost only integrate items that are strongly
coupled plasma-PFCs
These are some of the biggest challenges for
fusion, success in these areas would lead to an
attractive Demo.
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Fusion Ignition Research Experiment (FIRE)

• R 2.14 m, a 0.595 m
• B 10 T, ( 6.5 T, AT)
• Ip 7.7 MA, ( 5 MA, AT)
• PICRF 20 MW
• PLHCD 30 MW (Upgrade)
• Pfusion 150 MW
• Q 10, (5 - 10, AT)
• Burn time 20s (2 tCR - Hmode)
• 40s (lt 5 tCR - AT)
• Tokamak Cost 350M (FY02)
• Total Project Cost 1.2B (FY02)

1,400 tonne LN cooled coils
Mission to attain, explore, understand and
optimize magnetically-confined fusion-dominated
plasmas
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Characteristics of FIRE

• 40 scale model of ARIES-RS plasma
• All metal PFCs
• Actively cooled W divertor
• Be tile FW, cooled between shots
• T required/pulse TFTR 0.3g-T
• LN cooled BeCu/OFHC TF
• no neutron shield, allows small size
• 3,000 pulses _at_ full field (H-Mode)
• 30,000 pulses _at_ 2/3 field (AT-mode)
• X3 repetition rate since SNMS
• Site needs comparable to previous
• DT tokamaks (TFTR/JET).

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FIRE Plasma Systems are Similar to ARIES-AT

• kx 2.0, dx 0.7
• Double null divertor
• Very low ripple 0.3 (0.02)

• NTM stability LH current profile modification
  (?) at (5,2) _at_ 10T ECCD _at_ 180 GHz, Bo 6.6T

• 80 (90) bootstrap current
• 30 MW LHCD and 5 MW (25 MW capable) ICRF/FW for
  external current drive/heating

• n/nGreenwald 0.9, (ARIES-AT)
• H(y,2) 1.4 (ARIES-AT)
• High field side pellet launch allows fueling to
  core, and ?P/?E 5 (10) allows sufficiently low
  dilution

• No ext plasma rotation source
• Vertical and kink passive stability tungsten
  structures in blanket, feedback coils behind
  shield
• n1 RWM feedback control with coils - close
  coupled

• Tungsten divertors allow high heat flux
• Plasma edge and divertor solution balancing of
  radiating mantle and radiating divertor, with Ar
  impurity

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FIRE Plasma Regimes
H-Mode AT(ss) ARIES-RS/AT R/a 3.6 3.6
4 B (T) 10 6.5 8 - 6 Ip (MA)
7.7 5 12.3-11.3 n/nG 0.7 0.85 1.7-0.85 H(
y,2) 1.1 1.2 1.7 0.9 - 1.4 bN 1.8
4.2 4.8 - 5.4 fbs , 25 77 88 -
91 Burn/tCR 2 3 - 5 steady
Operating Modes Elmy H-Mode Improved
H-Mode Reversed Shear AT - OH assisted -
steady-state (100 NI)
H-mode facilitated by dx 0.7, kx 2, n/nG
0.7, DN reduction of Elms.
AT mode facilitated by strong shaping, close
fitting wall and RWM coils.
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0-D Power/Particle Balance Identifies Operating
Space for FIRE - AT

• Heating/CD Powers
• ICRF/FW, 30 MW
• LHCD, 30 MW
• Using CD efficiencies
• ?(FW)0.20 A/W-m2
• ?(LH)0.16 A/W-m2
• P(FW) and P(LH) determined at r/a0 and r/a0.75
• I(FW)0.2 MA
• I(LH)Ip(1-fbs)
• Scanning Bt, q95, n(0)/ltngt, T(0)/ltTgt, n/nGr, ?N,
  fBe, fAr

• Q 5 - 10
• Constraints
• ?flattop/?CR determined by VV nuclear heat (4875
  MW-s) or TF coil (20s at 10T, 50s at 6.5T)
• P(LH) and P(FW) max installed powers
• P(LH) P(FW) Paux
• Q(first wall) lt 1.0 MWm-2 with peaking of 2.0
• P(SOL) - Pdiv(rad) lt 28 MW
• Qdiv(rad) lt 8 MWm-2

Generate large database and then screen for
viable points
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ARIES-like AT Plasmas with Q 10 in FIRE
Q 5 - 10 accessible ?N 2.5 - 4.5
accessible fbs 50 - 90 accessible tflat/tCR
1 - 5 accessible
If we can access.. H98(y,2) 1.2 -
2.0 Pdiv(rad) 0.5 - 1.0 P(SOL) Zeff 1.5 -
2.3 n/nGr 0.6 - 1.0 n(0)/ltngt 1.5 - 2.0
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Steady-State High-b Advanced Tokamak Discharge
on FIRE
0 1 2
3 4
time,(current redistributions)
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q Profile is Steady-State During Flattop, t10 -
41s 3.2 tCR
Profile Overlaid every 2 s From 10s to 40s
li(3)0.42
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FIRE Plasma Technology Parameters
H-Mode AT(ss) ARIES-RS/AT R/a 3.6 3.6
4 B (T) 10 6.5 8 - 6 Ploss/Rx
(MW/m) 17 23 94 - 66 Prad-div (MWm-2)
5 lt 8 5 Prad-FW (MWm-2) 0.3 0.5
lt0.5 Pfusion (MWm-2) 5.5 5.5 6 - 5.3 Gn
(MWm-2) 2 2 4 - 3.3 Pn(MWm-3), VV 25
25 50 - 40
All Metal PFCs W divertor Be coated Cu
tiles FW Power Density ARIES divertor -
steady-state - water cooled, t 2s First wall
tiles - cooled between pulses t 40s
The FIRE divertor would be a significant step
toward an ARIES-like DEMO divertor.
FIRE AT performance is presently limited by
the first wall power (g, n) handling.
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RD Needed for Advanced Tokamak Burning
Plasma Scaling of energy and particle
confinement needed for projections of performance
and ash accumulation. Benchmark codes using
systematic scans versus density, triangularity,
etc. Determine effect of high triangularity
and double null on confinement, b-limits, Elms,
and disruptions. Continue RWM experiments to
test theory and determine hardware requirements.
Determine feasibility of RWM coils in a burning
plasma environment. Improve understanding
of off-axis LHCD and ECCD including effects of
particle trapping, reverse CD lobe on edge
bootstrap current and Ohkawa CD. Development
of a self-consistent edge-plasma-divertor model
for W divertor targets, and incorporation of this
model into core transport model.
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Areas of Major FIRE Activities for the Near Term
Advanced Tokamak Modes (ARIES as
guide) (k, d, A, SN/DN, bN, fbs, ) - RWM
Stabilization - What is required and what is
feasible? - Integrated Divertor and AT -
Plasma Control (fast position control, heating,
current-drive, fueling) High Power Density
Plasma Facing Components Development - High
heat flux, low tritium retention Diagnostic
Development and Integration Integrated
Simulation of Burning Plasmas
The goal is to develop advanced operating modes
that can be used as the design basis for FIRE.
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Concluding Remarks
FIRE would be able to access quasi-stationary
burning plasma conditions. In addition, a
reactor-relevantsteady-state advanced tokamak
operating mode with power densities approaching
ARIES-AT could be explored on FIRE. There are
a number of high leverage physics RD items to be
worked on for operation in the conventional mode
and the advanced mode for FIRE and ITER. There
needs to be an increased emphasis on physics RD
for advanced modes and high power density PFCs
that lead to an attractive fusion reactor.
The U.S. Administration has shown an interest in
fusion and has approved joining the ITER
negotiations. Congress has also shown interest
with Authorization bills that support ITER if it
goes ahead, and support FIRE if ITER does not go
ahead. This is consistent with the consensus in
the U.S. fusion community.
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The Terra Cotta Warriors have returned to fight
for fusion.