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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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.
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
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
“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)
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
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
Change of plasma characteristics with increasing lithium evaporation
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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
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*
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
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
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
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
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
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
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
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.
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
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
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
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.
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.
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.
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
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
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).
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
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
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.
New auditorium
Auditorium in the new ITER Headquarters building
“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.
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.
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.
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
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
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
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.
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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
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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
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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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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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..
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
