Advanced Tokamak Plasmas and the Fusion Ignition Research Experiment Charles Kessel Princeton Plasma...
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Transcript of Advanced Tokamak Plasmas and the Fusion Ignition Research Experiment Charles Kessel Princeton Plasma...
![Page 1: Advanced Tokamak Plasmas and the Fusion Ignition Research Experiment Charles Kessel Princeton Plasma Physics Laboratory Spring APS, Philadelphia, 4/5/2003.](https://reader036.fdocuments.in/reader036/viewer/2022062321/56649e505503460f94b477d1/html5/thumbnails/1.jpg)
Advanced Tokamak Plasmas and the Fusion Ignition Research
Experiment
Charles KesselPrinceton Plasma Physics Laboratory
Spring APS, Philadelphia, 4/5/2003
![Page 2: Advanced Tokamak Plasmas and the Fusion Ignition Research Experiment Charles Kessel Princeton Plasma Physics Laboratory Spring APS, Philadelphia, 4/5/2003.](https://reader036.fdocuments.in/reader036/viewer/2022062321/56649e505503460f94b477d1/html5/thumbnails/2.jpg)
What is an Advanced Tokamak?• The advanced tokamak plasma simultaneously
obtains– Stationary state– High plasma kinetic pressure ----> MHD stability– High self-driven current ----> Bootstrap current– Sufficiently good particle and energy confinement ---->
Plasma transport– Plasma edge that allows particle and power handling ---->
Boundary condition between hot core plasma and vacuum/solid walls
• The advanced tokamak is a recognition that the tokamak is an integrated system and requires control to succeed
• The advanced tokamak is a tough nut to crack
![Page 3: Advanced Tokamak Plasmas and the Fusion Ignition Research Experiment Charles Kessel Princeton Plasma Physics Laboratory Spring APS, Philadelphia, 4/5/2003.](https://reader036.fdocuments.in/reader036/viewer/2022062321/56649e505503460f94b477d1/html5/thumbnails/3.jpg)
TransportSafety factor
Pressure profileCurrent profile (bootstrap)
LHCD, FWCD, NBCD, ECCD, HHFW
NBI rotationPellet injection
Plasma shapingImpurity injection
RWM feedback
NTMfeedback
Divertorpumping
plasma
Ion/electron heating
Alpha heating
Appreciating the plasma’s integrated behavior is helping us learn to control it
![Page 4: Advanced Tokamak Plasmas and the Fusion Ignition Research Experiment Charles Kessel Princeton Plasma Physics Laboratory Spring APS, Philadelphia, 4/5/2003.](https://reader036.fdocuments.in/reader036/viewer/2022062321/56649e505503460f94b477d1/html5/thumbnails/4.jpg)
Next Step Devices Must Provide the Basis for Advanced Tokamak Reactor Regime
FIRE
Inductive
AT
KSTAR
FIRE AT is approaching the reactor AT regime
Present tokamak experiments are pushing the envelope
![Page 5: Advanced Tokamak Plasmas and the Fusion Ignition Research Experiment Charles Kessel Princeton Plasma Physics Laboratory Spring APS, Philadelphia, 4/5/2003.](https://reader036.fdocuments.in/reader036/viewer/2022062321/56649e505503460f94b477d1/html5/thumbnails/5.jpg)
Local Reduction of Energy, Particle, and Momentum Transport in Plasmas
By Manipulating:Magnetic field distributionMomentum injectionElectron/ion heatingCurrent distributionImpurity injectionD Pellet injection
we are learning to control the location and width of the transport reduction
thermal conductivity
temperatures density&velocity
magnetic field twist
center edge ASDEX-U
![Page 6: Advanced Tokamak Plasmas and the Fusion Ignition Research Experiment Charles Kessel Princeton Plasma Physics Laboratory Spring APS, Philadelphia, 4/5/2003.](https://reader036.fdocuments.in/reader036/viewer/2022062321/56649e505503460f94b477d1/html5/thumbnails/6.jpg)
Theory and Experiments Show That Powerful MHD Instabilities Can Be Controlled
HBT-EP, Columbia Univ.
DIII-D, General Atomics
![Page 7: Advanced Tokamak Plasmas and the Fusion Ignition Research Experiment Charles Kessel Princeton Plasma Physics Laboratory Spring APS, Philadelphia, 4/5/2003.](https://reader036.fdocuments.in/reader036/viewer/2022062321/56649e505503460f94b477d1/html5/thumbnails/7.jpg)
Impurities Can Control Where Power from the Plasma is Deposited
Power radiated onto high heat flux surfaces
Power radiated more uniformly throughout vessel
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Large Plasma Self-Driven Current Fractions are Being Attained
60-90% of the plasma current is driven by the plasma itself, from its pressure gradient
ASDEX-U, Germany
DIII-D,USA
Japan
![Page 9: Advanced Tokamak Plasmas and the Fusion Ignition Research Experiment Charles Kessel Princeton Plasma Physics Laboratory Spring APS, Philadelphia, 4/5/2003.](https://reader036.fdocuments.in/reader036/viewer/2022062321/56649e505503460f94b477d1/html5/thumbnails/9.jpg)
FIRE Has Adopted the AT Features
Identified by ARIES Reactor Studies • High toroidal field
• Double null
• Strong shaping
• Internal vertical position control coils
• Wall stabilizers for vertical and kink instabilities
• Very low toroidal field ripple
• ICRF/FW on-axis CD
• LH off-axis CD
• NTM stabilization from LHCD, ECCD, q>2
• Tungsten divertor targets
• Feedback coil stabilization of RWMs
• Burn times exceeding current diffusion times
• Pumped divertor/pellet fueling/impurity control to optimize plasma edge
![Page 10: Advanced Tokamak Plasmas and the Fusion Ignition Research Experiment Charles Kessel Princeton Plasma Physics Laboratory Spring APS, Philadelphia, 4/5/2003.](https://reader036.fdocuments.in/reader036/viewer/2022062321/56649e505503460f94b477d1/html5/thumbnails/10.jpg)
FIRE is Aggressively Pursuing AT Control Tools
![Page 11: Advanced Tokamak Plasmas and the Fusion Ignition Research Experiment Charles Kessel Princeton Plasma Physics Laboratory Spring APS, Philadelphia, 4/5/2003.](https://reader036.fdocuments.in/reader036/viewer/2022062321/56649e505503460f94b477d1/html5/thumbnails/11.jpg)
AT Physics Control Capability on FIRE
Strong plasma shaping and control
Pellet injectionDivertor pumpingImpurity injection
ICRF/FW (electron heating/CD) on-axis ICRF ion heating on/off-axis
LHCD (electron heating/CD) off-axis
ECCD off-axis (Ohkawa current drive)
RWM MHD feedback control
t(flattop)/t(curr diff) = 1-5
Diagnostics
MHD
J-Profile
P-profile
Flow-profile
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FIRE Pushes to Self-Consistently Simulate Advanced Tokamak Modes
0-D Systems Analysis:Determine viable operating point global parameters that satisfy constraints
Plasma Equilibrium and Ideal MHD Stability: (JSOLVER, BALMSC, PEST2, VALEN), Determine self-consistent stable plasma configurations to serve as targets
Heating/Current Drive: (LSC, ACCOME, PICES, SPRUCE, CURRAY), Determine current drive efficiencies and deposition profiles
Transport:(GLF23 and pellet fueling models to be used in TSC) Determine plasma density and temperature profiles consistent with heating/fueling and plasma confinement
Integrated Dynamic Evolution Simulations: (Tokamak Simulation Code, WHIST, Baldur) Demonstrate self-consistent startup/formation and control including transport, current drive, fueling and equilibrium
Edge/SOL/Divertor:(UEDGE) Find self-consistent solutions connecting the core plasma with the divertor
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FIRE AT Integrated Simulations Show Attractive Features
Q ≈ 5
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Advanced Tokamaks --- We Want to Have It Our Way
• The advanced tokamak is characterized by the features we need for a viable fusion power plant
• Access to this regime requires control of the plasma and we are learning how by penetrating its coupled physics
• FIRE is a next step burning plasma device– Utilizing experimental advanced tokamak accomplishments
– Adopting design features of advanced tokamak reactor designs
– Applying integrated simulation tools to project the advanced tokamak performance
• FIRE can bridge the AT physics gap from present experiments to the reactor regime