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Establishing the scientific basis for fusion energy and for
understanding the plasma universe
James W. Van Dam
Fusion Energy Sciences Office of Science
U.S. Department of Energy
April 26, 2013
FUSION ENERGY SCIENCES: Scientific Progress, Program Vision, and
the FY 2014 Budget Proposal
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2
Fusion Energy Sciences program supports both fusion and plasma
science
Advance the fundamental science of magnetically confined plasmas
for fusion energy
Pursue scientific opportunities and grand challenges in high
energy density plasma science
Support the development of the scientific understanding required
to design and deploy fusion materials
Increase the fundamental understanding of plasma science beyond
burning plasmas
The mission of the Fusion Energy Sciences (FES) program is to
expand the fundamental understanding of matter at very high
temperatures and densities and to build the scientific foundations
needed to develop a fusion energy source. This is accomplished by
the study of the plasma state and its interactions with its
surroundings.
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Fusion Energy Sciences: snapshot
Magnetic Confinement Fusion High Energy Density Plasmas
General Plasma Science
Enabling R&D
ITER Project (international partnership)
Facilities
DIII-D NSTX-U
Experimental Plasma Research
Diagnostics
Theory & Simulation, SciDAC
MST
International collaborations
Max Planck Princeton Research Center for Plasma Physics
Inertial Fusion Energy Science Materials in Extreme Conditions
Instrument (MECI) @ SLAC-LCLS
Joint Program with National Nuclear Security Administration
Fusion Materials Science
Enabling Technology
Advanced Design
NSF/DOE Partnership in Basic Plasma Science
Low Temperature Plasma
Basic Plasma Science Facility
Mission of the Fusion Energy Sciences program To expand the
fundamental understanding of matter at very high temperatures and
densities and build the scientific foundations needed to develop a
fusion energy source. This is accomplished by the study of the
plasma state and its interactions with its surroundings.
C-Mod
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The DIII-D tokamak: overview
DIII-D facility @ General Atomics
A world leader in fusion plasma science, and in ensuring ITER’s
scientific success
Extensive diagnostics, coupled to theoretical and computational
studies
Has flexible heating, current drive, and plasma control
systems
A highly collaborative program
• 440 researchers total • 320 non-GA researchers from:
– 21 US and 10 overseas universities, – 22 overseas research
groups – 4 national labs – 4 private industry R&D groups
Participation includes 17 post docs and 22 graduate students
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“Snowflake” divertor configuration
The Snowflake Divertor: Initial results: peak heat loads
reduced from 4-7 to 0.5-1 MW/m2
Creates poloidal magnetic field lines with snowflake shape
Flares out the plasma flow, decreasing heat fluxes
Earlier experiments on NSTX and TCV (Switzerland), and now
DIII-D, are promising first steps
Compatibility with attractive core plasmas to be
investigated
Snow- flake
Selected for post-deadline talk at IAEA Fusion Energy Conference
(Oct 2012, San Diego) 5
Recognized by an R&D 100 Award
http://www.pppl.gov/images/Jon_Vlad.jpg
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“Capture and suppress” instability
• Active feedback control of Neoclassical Tearing Mode using
fast steerable mirrors to direct electron cyclotron power applied
to plasma Plasma Control System
computes locations of q=2 surface in real time
EC power turned on and mirror positioned to drive current at q=2
surface
Real-time control allows m=2/n=1 stabilization with lower EC
power
Selected for post-deadline talk at IAEA Fusion Energy Conference
(Oct 2012, San Diego)
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Pellet pacing in ITER baseline scenario to control Edge
Localized Mode (ELM)
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1.3 mm pellets 100-150 m/s
• 12x higher ELM frequency • 12x lower ELM divertor heat pulse •
Minimal change in confinement • No fueling increase • Effective
impurity screening
βN=1.8 Pellet Shot Non-Pellet Shot
20 Hz
40 Hz
fpellet x qdiv = const
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National Spherical Torus Experiment
Operated by Princeton Plasma Physics Laboratory
Low aspect ratio, unique field line geometry
Test bed for assessing this configuration as potential compact
neutron source
A highly collaborative program: 217 researchers, including 150
non-PPPL from 21 US universities, 5 national labs, and 5 private
industry groups
New capabilities will enable exploration of high beta
science
• Scaling of transport with collisionality
• First-of-kind studies of electron thermal transport
• Flexible neutral beam current injection
Participation includes 17 post docs and 19 graduate students
NSTX NSTX-U
Toroidal field < 0.5 T < 1.0 T
Plasma current < 1 MA < 2 MA
Pulse length ~1.0 s ~ 5 s
NB heating 5-9 MW 10-18 MW
New solenoid Inner TF bundle, TF
joint, OH & inner PF coils
Upgraded TF coil support
structure
New PF coil support structure
Reinforce umbrella structure
Also: modify coil power system, protection system &
ancillary support systems
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Change of plasma characteristics with increasing lithium
evaporation
9
Ene
rgy
Con
finem
ent T
ime
(ms)
Pre-discharge lithium evaporation (mg)
Global parameters generally improve With no core Li
accumulation
ELM frequency declines - to zero Edge transport declines
As lithium evaporation increases, transport barrier widens,
pedestal-top χe reduced
R. Maingi, et al., PRL 107 (2011) 145004
New bootstrap current calculation (XGC0 code) improves agreement
with profile reaching kink/peeling limit before ELM
p p
0
Nor
m. s
urfa
ce a
vg. c
urre
nt
0.5 0.6 0.7 0.8 0.9 1.0
1.0
0.8
0.6
0.4
0.2
0.0 ψN
XGC0 model
Sauter model
Bootstrap current profile
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Analysis of NSTX database for disruption avoidance
• Disruption warning algorithm shows high probability of
success
– Based on combinations of single threshold based tests
Results ~ 98% disruptions flagged with at least
10ms warning, ~ 4% false positives False positive count
dominated by near-
disruptive events
Disruptivity
Physics results Low disruptivity at relatively high βN ~ 6;
βN / βNno-wall(n=1) ~ 1.3-1.5 • Consistent with specific
disruption
control experiments, RFA analysis Strong disruptivity increase
for q* < 2.5,
and at very low rotation
Warning Algorithms
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All discharges since 2006
βN
li q*
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2nd neutral beam relocated for NSTX-U
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• Beam box = 40 tons • Lid = 14 tons
• Transferred from TFTR to NSTX-U • Began work February 2009 •
30,000 hours (>17 person years)
for decontamination, refurbishment, relocation design
• 55 people were involved
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Center stack fabrication and assembly
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Machined conductor at Major Tool being prepared for shipment to
PPPL
Conductor after cooling tube installation and grinding
Cooling tube being soldered into conductor at PPPL
Conductor being removed from oven after sandblasting and
priming
Conductor being wrapped with fiberglass insulation Insulated
conductor being placed into mold
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NSTX Upgrade project review (December 2012)
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NSTX test cell (February 2013)
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Umbrella legs cut out
and replaced
4 Outer TF coils
removed
Second beamline in
place
Bay J/K neutral beam extension
welded to vessel
First plasma anticipated FY 2015
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Alcator C-Mod
Alcator C-Mod @ MIT – Very high magnetic field and compact
size highest heat fluxes in world to plasma-facing
components
– Dimensionless scaling studies for ITER and future reactors
– All-metal first walls – Emphasis on plasma-wall
interactions,
RF plasma heating, and disruption studies
• FY 2014 budget proposal – Facility to be shut down
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Student participation: 29 graduate students, also postdocs
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I-mode extrapolation to ITER Q=10 requires densification
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• Enter I-mode at low density (reduced Pthresh) • Stay in I-mode
while increasing density
– Fusion power increases as auxiliary power is decreased
• Experiments are needed for scaling with machine size and
B-field strength
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Field-aligned ICRF antenna reduces metallic impurity
generation
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• Important issue for metal machines like ITER • Hypothesis: RF
sheath rectification and
acceleration of ions into wall – Large RF potentials measured
far from
antenna • Antenna designed to minimize E|| • Results:
– Improved RF power handling – Reduced Mo radiation –
Discrepancies with models remain
• Further experiments and modeling required
Field-Aligned Antenna Standard Antenna
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Madison Symmetric Torus: Focused on the confinement of high-beta
fusion plasmas using minimal external magnetization A world leader
in reversed field pinch research located at the University of
Wisconsin, Madison Advancing basic plasma physics and links to
astrophysics (e.g., magnetic self-organization)
Madison Symmetric Torus and Experimental Plasma Research
emphasize discovery
FY 2014 emphasis for MST and EPR on expanding validated
predictive capability
Total number of scientists involved: 15, including 8 on-site
collaborators
Student participation: 4 post docs, 12 grad students, 12
undergrad students
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Experimental Plasma Research: Emphasizes stellarators, spherical
tori,
field-reversed configurations, and spheromaks
18 EPR projects partially support a total of 117 scientists,
engineers, and technicians and 45 graduate and undergraduate
students
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Phys. Rev. Lett 107, 065005 (2011)
Madison Symmetric Torus (MST) Program Highlights
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Powerful Ion Heating Due to Magnetic Reconnection
In MST, powerful ion heating occurs for magnetohydrodynamic
tearing magnetic reconnection, yielding an ion temperature that can
exceed the electron temperature with clear evidence of
non-collisional heating. This process has been used to help
maximize the plasma pressure and energy confinement for fusion
research.
Magee et al., Phys. Rev Lett. 107, 065005 (2011)
Bergerson et al., Phys. Rev Lett. 107, 255001 (2011)
Den Hartog et al., Phys. Rev Lett. 107, 155002 (2011)
Helical Equilibrium in Magnetic Self-Organization
A new behavior has been discovered recently whereby the plasma
spontaneously attains a 3D helical equilibrium in the reversed
field pinch of the MST. This can be thought of as relaxation to a
lower energy state. The core of the plasma is helical, much like
the plasma in a stellarator, but the boundary remains nominally
axisymmetric.
Fast Thomson Scattering Enables Study of Tearing Instability
New high time resolution measurements of the electron
temperature profile made with an upgraded Thomson Scattering system
on MST have enabled the study of sawtooth evolution of electron
thermal diffusion in different regions of the plasma. The
measurements are in rough agreement with the electron thermal
diffusion predicted by a high spectral resolution zero-β nonlinear
resistive magnetohydrodynamic simulation.
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Theory and Advanced Simulations
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• Theory: Advances scientific understanding of the fundamental
physical processes governing the behavior of magnetically confined
plasmas
• SciDAC: Advances scientific discovery in fusion plasma science
and materials science by exploiting leadership-class computing
resources and associated advances in computational science
– Successful partnership with ASCR and strong synergy with the
FES theory and experimental programs
• Resources: NERSC resources, INCITE resources at the OLCF and
ALCF Centers, and HPC resources allocated via the ALCC program are
critical for advancing the mission of these programs
– SciDAC projects collectively used more than 50% of the entire
FES NERSC allocation in AY 2012
EPSI: XGC edge simulations
GSEP: BAE simulations with GTC CEMM: M3D-C1 sawteeth simulations
CSPM: GS2 ITB simulations
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Diagnostic innovation program
X-ray imaging spectral spectrometer (XICS)
Measuring ion and electron temperature profiles
XICS is an important part of the PPPL collaboration with NIFS
(Japan)
Extends the Large Helical Device measurement capability to high
density regimes
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Far-infrared laser interferometry and
polarimetry Simultaneous measurement of
fluctuations and equilibrium properties of magnetic fields and
density in the plasma interior
Critical to understanding turbulence and confinement, and
towards ability to develop real-time plasma control
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General Plasma Science Program
NSF/DOE Partnership and Joint Effort • Individual Investigator:
Research of fundamental plasma science and
engineering issues awarded through annual joint NSF/DOE
solicitation – supporting 40 projects at 24 universities
• “User” Facility: Basic Plasma Science Facility (BaPSF) at UCLA
• Center for Magnetic Self-Organization (CMSO) – supporting DOE
Laboratory
involvement in NSF Physics Frontier Center
• Large Collaboration: Anti-hydrogen Trapping (non-neutral
plasma) for the international ALPHA collabroation at CERN
• International Collaboration: Max Planck-Princeton Center for
Plasma Physics
DOE Laboratory General Plasma Science
Individual and collaborative research addressing specific
applied plasma, laboratory, space, and astrophysical plasma issues
- competitive review in FY 2013
Plasma Science Centers • Center for Predictive Control of Plasma
Kinetics (PSC), lead: U Michigan • Center for Momentum Transport an
Flow Organization (CMTFO), lead: UCSD
Ongoing research involving 90+ graduate students 22
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General Plasma Science highlights
Plasma Activated Water
Traylor et al., J. Phys. D: Appl. Phys. 44, 47 2001 (2011)
Plasmas interacting with water can be controlled to create
antibacterial compounds, creating a useful disinfectant for up to
seven days, and a potential improvement over traditional heat and
chemical methods for sterilization of medical equipment and
wounds.
Trapped Anti-Hydrogen Anti-hydrogen atoms, synthesized from cold
plasmas of positrons and antiprotons and trapped in a magnetic
bottle, have been measured for the first time by using their
"spectra" to probe the internal structure of the anti-hydrogen
atom. This is an initial step toward possible new insights into the
difference between matter and antimatter.
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High Energy Density Laboratory Plasmas
MEC construction was completed December 2012.
Matter in Extreme Conditions (MEC) instrument combines the
unique LCLS beam with high power optical laser beams, and a suite
of dedicated diagnostics tailored for this field of science.
0.1 Mbar
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In FY 2014 budget proposal: • HEDLP program will be contracted
to focus on MEC at LCLS, a world-leading capability for broad
HEDLP science unique to the Office of Science. • FES will be
unable to support the Joint NNSA/FES HEDLP program in FY 2014. NNSA
will still
support elements of NNSA/FES joint program and other aspects of
HEDLP, including the Stockpile Stewardship Academic Alliance, and
still seeks FES engagement in program development.
• Elements of HEDLP are retained in FES General Plasma Science
portfolio.
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Largest PIC-code simulations by number of cores on Sequoia
supercomputer
• Researchers at LLNL performed record simulations using all
1,572,864 cores of Sequoia, the largest supercomputer in the
world
– Sequoia, based on IBM BlueGene/Q architecture and operated by
NNSA, is the first machine to exceed one million computational
cores
– It is also No. 2 on the list of the world’s fastest
supercomputers, operating at 16.3 petaflops (16.3 quadrillion
floating point operations per second)
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• The simulations are the largest particle-in-cell (PIC) code
simulations by number of cores ever performed
– These simulations allowed researchers, for the first time, to
model the interaction of realistic fast-ignition lasers with dense
plasmas in three dimensions with sufficient speed to explore a
large parameter space and optimize the design for ignition.
– Each simulation evolved the dynamics of more than 100 billion
particles for more than 100,000 computational time
steps--approximately an order of magnitude larger than previous
simulations of fast ignition.
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Materials in Fusion Environment
Plasma/surface interactions • Establishing boundary of a fusion
plasma. Plasma-facing
surface survival and renewal: cracking, annealing, fuel
retention. Also important for industrial applications.
Nuclear effects on materials and structures • Including the
effects of > 100 dpa on structure integrity,
helium creation in situ, and time-evolving properties
Harnessing fusion power • Extension to tritium breeding and
extracting fusion power
Factoid: Of the 10 most cited papers in Journal of Nuclear
Materials
during the past 5 years, 6 were authored by FES-funded
scientists
HFIR for irradiations
FMITS on SNS target
SNS can provide ITER-relevant neutrons for irradiation studies
of fusion materials 26
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Emerging global opportunities
EAST
W7-X
New class of super-conducting machines are paving the way to
ITER, and the U.S. is poised to maintain leadership through growing
partnerships.
SST-1
http://en.wikipedia.org/wiki/File:IPP_logo.png
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New large international facilities
EAST superconducting tokamak (Hefei, China) Goal: 1000s pulse, 1
MA
KSTAR superconducting tokamak (Daejon, S. Korea) Goal: 300s
pulse, 2 MA
Features: 2015 plan is 50-second high-power pulse, towards 300 s
goal. MHD mode control capability in place—an area US has pioneered
on NSTX and DIII-D and at universities.
Features: Superconducting magnets. Rapidly growing diagnostic
set. Heating: 2014 upgrades will yield heating capabilities
rivaling those of DIII-D
Phys. Rev. 107, 065005 (2011)
Stellarators: the world of 3D magnetic fields
W7-X (Greifswald, Germany) & Large Helical Device, (Toki,
Japan) US-built trim coils, power supplies, high heat flux divertor
components, and IR imaging diagnostics will support future
collaboration on W7-X (Germany). Innovative diagnostics on LHD
(Japan).
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Existing large international facilities
ASDEX-Upgrade tokamak (Garching, Germany) Features:
• All-metal coating (W) on plasma-facing components—recently
installed • Ion cyclotron wave heating and neutral beams • MHD
stability research complements DIII-D’s • ELM mitigation research,
inspired by US leadership in this area • Large diagnostic set and
advanced plasma control system
Phys. Rev. 107, 065005 (2011)
Joint European Torus (Abingdon, U.K.)
World’s largest tokamak – capable of DT – and a test bed for
ITER Features: • ITER-Like Wall (ILW) with all metal plasma-facing
components (Be
first wall, W divertor) installed recently--similar to ITER •
Alpha particle studies in tritium experiments (planned for 2014-15)
• High-power ion cyclotron RF wave heating & neutral beam
heating • Disruption mitigation research • Experience with remote
handling
http://en.wikipedia.org/wiki/File:IPP_logo.png
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International facilities can help study how to handle high heat
fluxes in a reactor
Reactor walls will operate hot, will likely be tungsten, and
will need to manage many MW/m2 for long periods of time.
Superconducting devices overseas will soon have this capability.
International partnerships will be critical for the US.
Partnerships supported with FY 2014 budget request
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US-Japan Implementing Agreement
• Past history – Thanks to the initiative of Prime Minister
Fukuda and President Carter, in
1979, the U.S. Secretary of Energy and the Japanese Minister of
Foreign Affairs signed a 10-year agreement to cooperate in energy
research and development. Shortly thereafter, the first U.S.-Japan
cooperative activity in fusion was begun with a diplomatic Exchange
of Notes.
– The U.S.-Japan Coordinating Committee on Fusion Energy (CCFE)
was created to oversee all such cooperative efforts, which began in
1980 with the JIFT program.
• Current status – The Research and Development Agreement
expired in Sept 2005 before it
could be renewed again, when the status of JA universities and
JAEA changed to that of independent administrative agencies
– Ongoing activities continued while a new Agreement was in
process – US Dept of State is assisting to finalize the new
Agreement, which will be
signed on April 30, 2013
• Past and present experience of US-Japan international
cooperation in fusion plasma research is now paying off in
partnership in ITER Project
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Tokamak Pit construction activity has accelerated
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ITER Project is moving forward rapidly
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All employees relocated to new site
16 November, as the last offices on the CEA site were being
vacated by ITER employees who had been assigned new offices within
the ITER site, the Rotogate rotated for the last time.
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New auditorium
Auditorium in the new ITER Headquarters building
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“Unique ITER Team”
The Unique ITER Team holds a briefing: ITER Director-General
Osamu Motojima called for an all-hands meeting in the Headquarters'
brand-new amphitheatre in order to brief the
ITER Organization staff on the outcome of the recent STAC and
MAC meetings.
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11th ITER Council Meeting
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The Eleventh ITER Council convened on 28-29 November 2012 at
ITER Headquarters. The Council noted the strong measures that have
been taken by the ITER Organization and the Domestic Agencies to
realize strategic schedule milestones and to develop new corrective
measures for critical systems. The next ITER Council meeting is
scheduled to take place in Japan in June 2013.
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10th ITER Council Meeting was held in the U.S. in June 2012
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"The US is committed in the project," stated Steven Chu, United
States Secretary of Energy (right) as the tenth ITER Council began
on 20 June in Washington, DC. Next to Chu: Council Chair Hideyuki
Takatsu, speaking; ITER Director-General Osamu Motojima; and, right
to left, deputies Rem Haange, Rich Hawryluk and Carlos
Alejaldre.
The participants to the Tenth ITER Council
Meeting stand together in the Ronald Reagan
Building in Washington, D.C., on Thursday, 21
June.
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ITER advisory committees
The STAC Chairman, Joaquin Sanchez, discussing with the STAC
secretary Alberto Loarte (right)
and David Campbell, Head of the Directorate for Plasma
Operations
Participants at the most recent MAC meeting
Science and Technology Advisory Committee of the ITER
Council
Management Advisory Committee of the ITER Council
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Recent major fusion meetings held in US
• 10th ITER Council Meeting – Hosted by the US in Washington,
DC, June
20-21, 2012
• 24th IAEA Fusion Energy Conference – Hosted by the US in San
Diego, CA, October
8-13, 2012
• Six ITPA topical group meetings – Also hosted by the US in San
Diego, the week
after the IAEA Fusion Energy Conference
• IAEA DEMO Programme Workshop – Hosted at UCLA Oct 15-18,
2012
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About 80% of US ITER funding is for in-kind hardware
contributions built in US
In-kind hardware contributions are managed at U.S. ITER Project
Office (at Oak Ridge National Laboratory) Procurements and
fabrication are well underway
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The heart of the ITER facility will be the Tokamak Complex,
comprising the Tokamak Building, the Diagnostic Building, and the
Tritium Plant. The seven-story Complex, measuring 118 m by 80 m and
towering 57 m above the platform, will contain more than 30
different plant systems, including cooling systems and electrical
power supplies, all having physical as well as functional
interfaces.
Complex integration tasks
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Major central solenoid fabrication advancing on schedule
• 13 Tesla • 5.5 GJ • 1.2 T/s • 100 tons/pack
6 independent coil packs
Technical problems with Japanese conductor solved using U.S.
project management techniques
Tooling stations for each winding pack using the Japanese
conductor are being assembled at General Atomics in Poway, CA.
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Over 75 hardware prototypes are under development and
testing
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Recent FESAC reports
• “Priorities of the Magnetic Fusion Energy Science Program” –
Approved at January 31, 2013, FESAC meeting – Response to charge
asking FESAC to prioritize the elements of the non-ITER
part of the MFE science program for three budget scenarios
• “Prioritization of Proposed Scientific User Facilities for the
Office of Science” – Approved at March 15, 2013, FESAC meeting –
Response to charge (to all Office of Science program office federal
advisory
committees) on prioritization of scientific facilities for
period 2014-2024
Both reports are available on the FESAC web page at:
http://science.energy.gov/fes/fesac/reports/
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• This new list of prioritized science facilities will be the
successor to Facilities for the Future of Science: A Twenty-Year
Outlook (2003)
New Office of Science facility list
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World fusion science landscape will look considerably different
in a decade
ITER will begin operations in the next decade
The FY 2014 budget outlines a sustainable plan for support of
ITER construction. These contributions are intimately linked to
those of our partners and must be delivered on time to avoid
overall construction delays and cost increases to the Member
states. The annual spending is capped.
The US research effort has to effectively use and reap the
maximal benefit
from ITER with a world-leading workforce
The FY 2014 budget supports a broad, impactful program in
experiment, theory, and computation at labs, universities and
industry. FES focuses on ITER-related burning plasma science but
invests in broader research as well. Despite reductions in domestic
research as compared to FY 2012, the budget furthers the
development of a strong, world leading scientific workforce
educated in the fusion and plasma sciences on a broad front. FES
projects that this budget will support the research education of
over 240 graduate student FTEs, well over 300 individuals.
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World fusion science landscape will look considerably different
in a decade (2)
There will be mature, cutting-edge research facilities around
the globe addressing ITER needs and looking beyond it
The FY 2014 budget invests in international partnerships, to
enable the US to be on the leading edge of plasma-wall interaction
science, the science of long pulse in tokamaks, both of high
relevance to ITER and steady-state stellarators. All of these
sensibly lever US strengths and will enable the US to assert
leadership in these areas.
Leverage will become increasingly important in the fusion and
plasma
sciences with tough budgets
The FY 2014 budget presents a responsible approach to tough
budgetary times. ITER represents the height of leveraging
capabilities internationally. While the scope of HEDLP is reduced,
what is maintained is a cross-SC partnership with BES at LCLS that
will generate first-of-a-kind science. International partnerships
will target high leverage opportunities that build on US strengths.
General plasma science portfolio includes a strong partnership with
NSF that is highly effective in both doing great science and in
developing young plasma scientists. Fusion computing levers
partnership with ASCR through the SciDAC program.
46
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• The federal government first operated under a six-month
Continuing Resolution SC program offices were given 47% of funding
for first six months Many first-time new awards under solicitations
were held up
• Sequestration took effect on March 1 • A full-year Continuing
Resolution was enacted on March 22
The FY 2013 Spend Plan is in the process of being approved
FY 2013 federal budget
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FY 2014 budget proposal summary
FY 2012 Enacted
FY 2014 Request
Science DIII-D Research 30,974 28,200 C-Mod Research 10,595 0
International Research 8,325 8,300 Diagnostics 3,538 3,500 Other
7,950 8,312 NSTX Research 16,940 17,500 Experimental Plasma
Research 10,965 10,500 HEDLP 25,257 6,575 MST Research 6,000 5,700
Theory 24,450 20,670 SciDAC 8,310 6,875 General Plasma Science
16,706 15,000 SBIR/STTR 0 6,672 Total, Science Research 170,010
137,804
Fusion Energy Sciences FY 2014 Budget Request
(Budget Authority in thousands)
FY 2012 Enacted
FY 2014 Request
Facility Operations DIII-D 38,715 36,960 C-Mod 18,217 0 NSTX
33,959 36,300 Other, GPE, and GPP 1,565 900
MIE: US Contributions to ITER Project 105,000 225,000
Total, Facility Operations 197,456 299,160 Enabling R&D
Plasma Technology 14,652 11,660 Advanced Design 2,611 1,400
Materials Research 8,228 8,300 Total, Enabling R&D 25,491
21,360 Total, Facility Ops 222,947 320,520 Total, Fusion Energy
Sciences 392,957 458,324
Major changes compared to FY 2012 (enacted) 1. US ITER Project
increase of $120M, to capped level of
$225M 2. Alcator C-Mod ceases operations 3. HEDLP scope
reduced
48
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General Plasma Science
HEDLP International
Research
**Other Enabling R&D *Small Scale
MFE
ITER Project
General Plasma Science
HEDLP International
Research
**Other
Enabling R&D
*Small Scale MFE
DIII-D Operations
DIII-D Research
NSTX Operations
NSTX Research
Theory & SciDAC
Science: $160,064,000 • Major Tokamak's Research (45.7 %)
• DIII-D • NSTX • Theory & SciDAC
• Small Scale Magnetic Fusion Energy (10.1 %) • Experimental
Plasma Research • Madison Symmetric Torus
• Enabling R&D (13.3 %) • Plasma Technology • Advanced
Design • Materials
• International Collaborations (5.2 % ) • High Energy Density
Laboratory Plasmas (4.1 %) • General Plasma Science (9.4 %)
Facility Operations: $299,160,000 • ITER at $225M, per
Administration agreement (75 %) • DIII-D (12 %) • NSTX Upgrade (12
%) • GPE/GPP/Infrastructure
At a Glance: FES at $458M in FY 2014
Without ITER
Total FES program
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Hatched areas indicate project and operations expenses * Smaller
Scale MFE includes Experimental Plasma Research portfolio and MST
** Other includes SBIR/STTR, Diagnostics, and
GPE/GPP/Infrastructure
Major Tokamaks Research and Operations,
Theory, Simulation
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Recent Early Career Awardees
Daniel Sinars of Sandia National Laboratories wins the
Presidential Early Career Award for Science and Engineering
(PECASE)
“For developing innovative techniques to study the properties of
instabilities in magnetized-high-energy-density plasma, enabling
quantifiable comparison between experiment and simulation needed
for validating cutting-edge radiation-hydrodynamics codes, and for
demonstrating substantial leadership qualities in
high-energy-density-laboratory-plasma (HEDLP) physics.”.
FY 2010
Stanislav Boldyrev, U Wisc.
Tobin Munsat, U Colorado
Jean Paul Allain, Purdue Univ.
Luisa Chiesa, Tufts University
Jong-Kyu Park, PPPL
Vlad Soukhanovskii, LLNL
FY 2011
Kai Germaschewski, UNH
Christoph Niemann, UCLA
Francesco Volpe, U Wisc.
Anne White, MIT
Daniel Sinars, SNL
Ezekial Unterberg, ORNL
FY 2012
Felix Parra Diaz, MIT
Jaime Marian, LLNL
Nicholas Commaux, ORNL
Andreas Kemp, LLNL
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51
Recent Nuclear Fusion journal prizes
Awarded annually (since 2006) to recognize outstanding work
published in Nuclear Fusion Based on citation record and scientific
impact Past awardees: Luce (2006), Angioni (2007), Evans
(2008),
Sabbagh (2009), Rice (2010) 5 of 7 awards have gone to U.S.
scientists (highlighted in red)
2011 Prize to Hajime Urano (JAEA): Dimensionless parameter
dependence of
H-mode pedestal width using H and D plasmas in JT-60U
2012 Prize to Patrick Diamond (UCSD/NFRI): Non-diffusive
transport transport of momentum and origin of
spontaneous rotation in tokamaks
2011 and 2012 prizes were awarded at the biennial IAEA Fusion
Energy Conference (San Diego, October 2012)
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52
E.O. Lawrence Award
Citation: “Riccardo Betti will be honored for a series of
impactful theoretical discoveries in the physics of inertial
confinement fusion including seminal transformative work on
thermonuclear ignition, hydrodynamic instabilities and implosion
dynamics, and the development of innovative approaches to ignition
and high energy gains”.
Riccardo Betti of the University of Rochester received E. O.
Lawrence Award (2012)
Professor Betti received the E. O. Lawrence Award in the area of
Fusion and Plasma Science during a ceremony hosted by Secretary of
Energy Steven Chu on May 21, 2012. In addition to his research in
inertial confinement fusion, Prof. Betti has in parallel maintained
a strong theoretical research effort in magnetic confinement
fusion, with well-known papers on energetic particle physics,
tokamak equilibria with toroidal flow, and macroscopic
instabilities such as the resistive wall mode. He is the director
of the Fusion Science Center for Extreme States of Matter, funded
by the DOE Fusion Energy Sciences..
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Significant scientific opportunity is enabled with FY 2014
proposed budget
Fusion can be an important player in the world energy picture
later in this century.
The next essential step for fusion, burning plasma science
enabled by ITER, is strongly supported with a responsible spending
approach.
The US program supported in this budget will enable ITER to
bring great benefit to the US – The elements in it are strong, and
effects of tough choices can be mitigated. Cross-agency and
international leverage is critical.
Stewardship of a broad plasma sciences program is enabled
through cross-office and cross-agency leverage.
Slide Number 1Fusion Energy Sciences program supports both
fusion and plasma scienceFusion Energy Sciences: snapshotThe DIII-D
tokamak: overview“Snowflake” divertor configuration“Capture and
suppress” instabilityPellet pacing in ITER baseline scenario to
control Edge Localized Mode (ELM)National Spherical Torus
ExperimentChange of plasma characteristics with increasing lithium
evaporationAnalysis of NSTX database for disruption avoidance2nd
neutral beam relocated for NSTX-UCenter stack fabrication and
assemblyNSTX Upgrade project review (December 2012)NSTX test cell
(February 2013)Alcator C-Mod I-mode extrapolation to ITER Q=10
requires densificationField-aligned ICRF antenna reduces metallic
impurity generationMadison Symmetric Torus and Experimental Plasma
Research emphasize discoveryMadison Symmetric Torus (MST) Program
HighlightsTheory and Advanced SimulationsDiagnostic innovation
programGeneral Plasma Science ProgramGeneral Plasma Science
highlightsHigh Energy Density Laboratory PlasmasSlide Number
25Materials in Fusion EnvironmentEmerging global opportunitiesNew
large international facilitiesExisting large international
facilitiesSlide Number 30US-Japan Implementing AgreementTokamak Pit
construction activity has acceleratedAll employees relocated to new
siteNew auditorium“Unique ITER Team”11th ITER Council Meeting10th
ITER Council Meeting was held in the U.S. in June 2012ITER advisory
committeesRecent major fusion meetings held in USAbout 80% of US
ITER funding is for in-kind hardware contributions built in USMajor
central solenoid fabrication advancing on scheduleOver 75 hardware
prototypes are under development and testingRecent FESAC reportsNew
Office of Science facility listWorld fusion science landscape will
look considerably different in a decade World fusion science
landscape will look considerably different in a decade (2)FY 2013
federal budgetFY 2014 budget proposal summary�Slide Number 49Recent
Early Career AwardeesRecent Nuclear Fusion journal prizesE.O.
Lawrence AwardSignificant scientific opportunity is enabled with FY
2014 proposed budgetSlide Number 54Fusion Energy Sciences:
researchFusion Energy Sciences: facilitiesAll magnetic confinement
concepts benefit from burning plasma scienceEnabling R&D
researchHigh-T superconductor cablesNew high-power depressed
collector gyrotron in operation at DIII-DThe approach for US ITER
support: no more than $225M per yearSlide Number 62