Fusion Energy Sciences
Overview
The Fusion Energy Sciences (FES) program mission is to expand the fundamental understanding of matter at very hightemperatures and densities and to build the scientific foundation needed to develop a fusion energy source. This isaccomplished through the study of plasma, the fourth state of matter, and how it interacts with its surroundings.
The next frontier for all of the major fusion research programs around the world is the study of the burning plasma state, inwhich the fusion process itself provides the dominant heat source for sustaining the plasma temperature (i.e., self-heating).
Production of strongly self-heated fusion plasma will allow the discovery and study of new scientific phenomena relevant tofusion energy. These include the effects of highly energetic fusion-produced alpha particles on plasma stability andconfinement; the strongly nonlinear coupling that will occur among fusion alpha particles, pressure-driven self-generated
current, turbulent transport, and boundary-plasma behavior; the properties of materials in the presence of high heat andparticle fluxes and neutron irradiation; and the self-organized nature of plasma profiles over long time scales.
To achieve these research goals, FES invests in flexible U.S. experimental facilities of various scales, international
partnerships leveraging U.S. expertise, large-scale numerical simulations based on experimentally validated theoreticalmodels, development of advanced fusion-relevant materials, and invention of new measurement techniques.
FES also supports discovery plasma science, including research in laboratory plasma astrophysics, low-temperatureplasmas, small-scale magnetized plasma experimental platforms, and high-energy-density laboratory plasmas. Some of thiswork is jointly supported with the National Science Foundation (NSF).
Highlights of the FY 2018 Budget Request
Strategic choices in this Budget Request were informed by the reductions in the overall FY 2018 Office of Science Budget
Request, priorities described in “The Office of Sciences’ Fusion Energy Sciences Program: A Ten-Year Perspective”(submitted to Congress in 2015), and the research opportunities identified in a series of community engagement workshops
held in 2015. Priorities include keeping FES user facilities world-leading, increasing investment in massively parallel
computing, supporting high-impact research in fusion materials, strengthening partnerships for access to international
facilities with unique capabilities, learning how to predict and control transient events in fusion plasmas, and continuing
stewardship of discovery plasma science (e.g., via intermediate-scale basic facilities). Building on the workshops and theten-year strategic perspective, FES has recently commissioned a study by the National Academies of Science about research
priorities for burning plasma science. Also, SC has charged the Fusion Energy Sciences Advisory Committee (FESAC) toinvestigate the potential for transformative developments in fusion science and technology.
Notable changes in the FY 2018 Request include:

Increased support for DIII-D program—Total funding for the DIII-D program is increased to address the high-priority
fusion science issues identified by the community research needs workshops held in FY 2015 and to support enhanced
involvement of collaborating university and laboratory researchers in these programs. Funding will support 18 weeks ofoperation and greater involvement of the National Spherical Torus Experiment Upgrade (NSTX-U) scientists in the DIII-D
program while repairs of NSTX-U are underway. It will also support increased collaborations by Massachusetts Instituteof Technology (MIT) researchers following the closure of the Alcator C-Mod facility in FY 2017.

Continued support for NSTX-U program research and recovery activities—The NSTX-U facility is down for recovery(assessment and repair) during FY 2017, and this will continue in FY 2018. In FY 2016, a series of deficiencies were
found in the design and construction of the NSTX-U device, which prompted the Princeton Plasma Physics Laboratory(PPPL) to cease operation and carry out thorough design verification and validation reviews. The FY 2018 NSTX-U
Operations budget will support high-priority activities to implement repairs and corrective actions required to obtainrobust, reliable research operations. The NSTX-U Research budget will fund the continued analysis of high-impact dataacquired during the FY 2016 run campaign, a focused effort on physics topics that directly support the recovery of

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robust NSTX-U plasma operations, and enhanced involvement of university collaborative research at other facilities tosupport NSTX-U research program priorities.


Reduced support for ITER—This reduction reflects the decrease in the DOE science budget and U.S. concerns about thecost and schedule of ITER.



Increased support for Scientific Discovery through Advanced Computing (SciDAC)—Funding for SciDAC is increased toaddress high-priority research in tokamak disruptions and boundary physics as identified in the 2015 community
workshops, and to accelerate development of a whole-device modeling capability, in partnership with the Advanced
Scientific Computing Research (ASCR) program.

Continued support for Long Pulse Tokamak and Stellarator research—Funding for Long Pulse Tokamak is maintained forresearch opportunities for U.S. scientists on superconducting tokamaks with world-leading capabilities. Funding forLong Pulse Stellarator will enable U.S. research teams to take full advantage of U.S. hardware investments on
Wendelstein 7-X (W7-X) and enhance the scientific output on this device.

Support for Fusion Nuclear Science and Materials Research—Funding for Fusion Nuclear Science and Materials
Research is refocused on fundamental science.

Support for Discovery Plasma Science—Research and operations on intermediate-scale user facilities will beemphasized to pursue opportunities identified in the 2015 community workshops.

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Fusion Energy Sciences
Funding ($K)
FY 2016 Enacted a
Fusion Energy Sciences
Burning Plasma Science: Foundations
Advanced Tokamak
Spherical Tokamak
Theory & Simulation
GPE/GPP/Infrastructure
Total, Burning Plasma Science: Foundations
Burning Plasma Science: Long Pulse
Long Pulse: Tokamak
Long Pulse: Stellarators
Materials & Fusion Nuclear Science
Total, Burning Plasma Science: Long Pulse
Discovery Plasma Science
Plasma Science Frontiers
Measurement Innovation
SBIR/STTR & Other
Total, Discovery Plasma Science
Subtotal, Fusion Energy Sciences
Construction
14-SC-60 International Thermonuclear Experimental Reactor (ITER)
Total, Fusion Energy Sciences

FY 2017 Annualized
CR b

FY 2018 Request

FY 2018 vs FY 2016

101,754
76,19533,8105,875
217,634-

86,00059,10032,5000177,600-15,754 - 15.5 %-17,095 - 22.4 %-1,310 - 3.9 %-5,875 - 100 %-40,034 - 18.4%

8,944
7,079
24,05340,076

-

8,500
7,000
19,82335,323-444 - 5.0 %-79 - 1.1 %-4,230 - 17.6 %-4,753 - 11.9 %46,504
3,568
15,21865,290323,000-

23,600900
9,517
34,017
246,940-22,904 - 49.3 %-2,668 - 74.8 %-5,701 - 37.5%-31,273 - 47.5%-76,060 - 23.5%

63,000309,940-52,000 - 45.2 %-128,060 - 29.2 %115,000
438,000--

SBIR/STTR:
 FY 2016 Transferred: SBIR: $9,333,000; STTR: $1,400,000
FY 2018 Request: SBIR $XXX and STTR $XXX

a The FY 2016 Enacted level includes SBIR and STTR and reflects updates through the end of the fiscal year.

b FY 2017 Annualized CR amounts reflect the P.L. 114-254 continuing resolution level annualized to a full year. These amounts are shown only at the congressional control level and above,

below that level, a dash (-) is shown.

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Fusion Energy Sciences
Explanation of Major Changes ($K)
Burning Plasma Science: Foundations: Funding for tokamak research decreases due to the shutdown of the Alcator C-Mod facility in FY 2017.
DIII-D program funding increases to support the enhanced collaboration by university and laboratory personnel, including MIT and NSTXU scientists, in the DIII-D program. Funding for SciDAC increases to accelerate progress toward whole-device modeling. Funding for the
NSTX-U program will support the repair of the facility, while DIII-D funding will enable 18 weeks of operations. All GPE/GPP funding isdeferred.

FY 2018 vs FY 2016-$40,034

Burning Plasma Science: Long Pulse: Funding for Materials and Fusion Nuclear Science decreases with an emphasis on addressing thehighest priority issues in both program elements.

-$4,753

Discovery Plasma Science: Overall funding is decreased. For General Plasma Science and Exploratory Magnetized Plasma, research andoperations of intermediate-scale, scientific user facilities are emphasized. For High Energy Density Laboratory Plasma, the focus remains
on supporting research utilizing the Matter in Extreme Conditions instrument of the Linac Coherent Light Source facility at the SLAC
National Accelerator Laboratory at Stanford University.

-$31,273

Construction: Funding decreases for the U.S. Contributions to ITER project.

-$52,000

Total Funding Change, Fusion Energy Sciences-$128,060

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Basic and Applied R&D Coordination
FES coordinates within DOE and with other federal agencies on science and technology issues related to fusion and plasma
science. Within SC, FES operates the Matter in Extreme Conditions (MEC) instrument at the Linac Coherent Light Source(LCLS) user facility operated by Basic Energy Sciences (BES). In addition, FES carries out a discovery-driven plasma science
research program in partnership with the NSF, with research extending to a wide range of natural phenomena, including
the origin of magnetic fields in the universe and the nature of plasma turbulence. Also, FES operates a joint program with
the National Nuclear Security Administration (NNSA) in High Energy Density Laboratory Plasma (HEDLP) physics. Bothprograms involve coordination of solicitations, peer reviews, and workshops. The FESAC provides technical andprogrammatic advice to FES and NNSA for the joint HEDLP program.
Program Accomplishments
Important for fusion reactors: novel stable, efficient operating scenario with low-rotation developed—Most current-day
tokamaks have plasmas with significant rotation, due to the large torque applied by neutral ion beams used for heating.
However, future fusion power plants will operate with almost no rotation. The DIII-D tokamak facility at General Atomics,
with its ability to balance the neutral beam torque while still heating (with up to 10 megawatts of power), has uniquecapabilities to study low-torque regimes. Normally, rotation is needed to suppress plasma instabilities. Recently, however,scientists on DIII-D found that fusion performance while operating in the Quiescent H-Mode scenario (which is free of
dangerous edge localized mode instabilities) actually improved as the rotation was decreased. The improvement occurs
because the plasma undergoes a bifurcation into a new state characterized by increased pedestal height and width,
resulting in enhanced global confinement.
Towards a possible breakthrough for reactor wall materials: lithium wall contains plasma without cooling it—In large
tokamaks with tungsten walls, the edge plasma must be cooled to low temperatures (a few tens of electron-volts) in orderto reduce sputtering of the wall, which can lead to heavy tungsten impurities beginning to accumulate in the plasma. But
lower temperatures at the edge cause the plasma to be less hot in the core, which then degrades fusion performance. The
Lithium Tokamak Experiment, a medium-scale tokamak at PPPL, found that lithium-coated walls can handle edge plasma
temperatures higher than 200 electron-volts, with little influx of lithium and no impact on performance. Another advantage
is that the resulting temperature profile is essentially flat from the edge to the core, which potentially avoids deleterious
instabilities driven by a temperature gradient.
Massively parallel computation enables essential step towards predictive capability: simulations of electrical current
generation in tokamaks—The conventional understanding of how intrinsic electrical current (the so-called bootstrap
current) is generated is that the current is carried by charged particles that flow around the doughnut-shaped tokamak
without getting magnetically trapped at the outboard side of the confinement configuration. New massively parallel
numerical simulations, performed by scientists in the SciDAC Edge Physics Simulation Center (a partnership with ASCR)
have, however, shown that the bootstrap current in the boundary region of the plasma is carried predominately by themagnetically trapped particles. This new understanding will greatly improve the prediction of the properties of theboundary plasma, including the important “pedestal” region, which plays a critical role in determining the overall fusion
performance of the plasma.
Extending the reach of U.S. fusion science: collaborative research during the initial operation of W7-X—The U.S. is aninternational partner in the new Wendelstein 7-X facility, the world’s largest stellarator, which began operation in early
FY 2016. U.S. scientists helped map out the magnetic field line surfaces with an electron beam, to confirm magnetic coilalignment. During the first plasma operation period, the U.S. collaboration team used the set of five trim coils it hadconstructed to measure intrinsic field errors, calibrate magnetic measuring instruments, and perturb the plasma. Also, theU.S. scientists used their x-ray imaging crystal spectrometer instrument to make the first measurements of time-resolved
ion temperature profiles, together with high-quality electron temperature profiles. The spectrometer also measured plasma
flow and core impurity transport – critical for reactor design. The U.S. participated in the March 2016 celebration event at
which German Chancellor Angela Merkel officially dedicated this new fusion research facility.
Essential for developing attractive materials for fusion reactors: first-of-a-kind materials irradiation experiments—The U.S.
and Japan have a five-year collaboration project to study the feasibility of using a helium-cooled divertor made out oftungsten material for future fusion devices. Recently, the collaborating scientists began a landmark series of irradiation
experiments on the High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory (ORNL). A shielded gadolinium rod is
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used to absorb the high thermal-neutron flux in the water-cooled HFIR reactor and thus achieve the appropriate ratio
between displacement damage and transmutation content that is expected in a fusion power plant. The tungsten material
samples thus being irradiated will yield unique understanding about the effects of fusion-type neutrons on their thermomechanical and fuel retention properties.
U.S. Contributions to ITER First Plasma subproject more than 50% complete—The U.S. completed the fabrication anddelivery of over 21,000 feet of superconductor cable, more than enough to wind one of the eighteen Toroidal Field coils.
Four U.S. industrial companies produced this superconductor. Additionally, the U.S. completed the fabrication and deliveryof all of its components for the Steady State Electrical Network, needed to provide power for construction activities, as well
as for plasma operations at ITER. Lastly, successful winding of the first two Central Solenoid superconducting magnet
modules was completed. Each Central Solenoid module is fabricated from approximately 6,000 meters of niobium-tin
superconductor. After winding and assembly, each completed module will undergo heat treatment, insulation, vacuum
pressure impregnation, and final testing at the cryogenic operating temperature (4 degrees Kelvin). The Central Solenoid,
an enormous electromagnet that is considered the "heartbeat of the ITER device," consists of six stacked magnet modules
surrounded by a support structure. When assembled, the entire Central Solenoid and associated structures will be over 42
feet tall, weigh over 1,100 U.S. tons, and produce a very strong magnetic field (13 Tesla).
Exotic solar phenomena explained in the lab: pulsating reconnection driven by three-dimensional (3D) flux-rope
interactions—In high-temperature plasmas, magnetic field lines can reconnect and release stored energy as the magnetic
field undergoes topological changes. Although the two-dimensional dynamics of magnetic reconnection has been
extensively studied, most applications in space and astrophysical plasmas are inherently three-dimensional. In a laboratory
experiment at UCLA, researchers measured the 3D electric and magnetic fields resulting from the interaction of twomagnetic flux “ropes” generated between a cathode and anode. The ropes were observed to bounce and reconnect in aperiodic pulsating fashion. These results provide the first direct experimental test of reconnection within a quasi-separatrix
layer (where magnetic field lines separate rapidly).
Science of the interior of giant planets accessed in the lab: liquid metallic hydrogen observed for the first time—The planet
Jupiter is 70% composed of hydrogen, with the outer layer made of familiar molecular hydrogen (as on Earth), butsurrounding the core an exotic state of hydrogen, called liquid metallic hydrogen, that requires extremely high pressures toexist. Researchers have been trying to observe this metallic state in the laboratory ever since it was predicted 80 years ago.
High-power lasers can provide the high pressures necessary to induce the insulator-to-metal transition of hydrogen.
Recently, SLAC scientists and their collaborators were able to observe this transition at a pressure of 250,000 atmospheres,using one laser beam to compress deuterium (a hydrogen isotope) and another laser beam to produce very shortwavelength x-rays that can probe the hydrogenic transition. These results provide insight into the physical properties ofgiant planets and also into the design of inertially confined fusion experiments with deuterium as a fuel.

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Fusion Energy Sciences
Burning Plasma Science: Foundations
Description
The Burning Plasma Science: Foundations subprogram advances the predictive understanding of plasma confinement,
dynamics, and interactions with surrounding materials. Among the activities supported by this subprogram are:






Research at major experimental facilities aimed at resolving fundamental advanced tokamak and spherical torus
science issues.
Research on small-scale magnetic confinement experiments to elucidate physics principles underlying toroidal
confinement and to validate theoretical models and simulation codes.
Theoretical work on the fundamental description of magnetically confined plasmas and the development of advanced
simulation codes on current and emerging high-performance computers.
Research on technologies needed to support the continued improvement of the experimental program and facilities.
Support for infrastructure improvements at Office of Science laboratories conducting fusion research.

Research in the Burning Plasma Science: Foundations area in FY 2018 will focus on high-priority challenges andopportunities in the areas of transients in tokamaks, plasma-material interactions, and integrated modeling, as identified by
the community research needs workshops held in FY 2015.
Advanced Tokamak
The DIII-D user facility at General Atomics in San Diego, California, is the largest magnetic fusion research experiment in the
U.S. and can magnetically confine plasmas at temperatures relevant to burning plasma conditions. Researchers from the
U.S. and abroad perform experiments on DIII-D for studying stability, confinement, and other properties of fusion-grade
plasmas under a wide variety of conditions. The DIII-D research goal is to establish the scientific basis to optimize thetokamak approach to magnetic confinement fusion. Much of this research concentrates on developing the advanced
tokamak concept, in which active control techniques are used to manipulate and optimize the plasma to obtain conditions
scalable to robust operating points and high fusion gain for future fusion reactors. Another high-priority DIII-D research area
is foundational fusion science, pursuing a basic scientific understanding across all fusion plasma topical areas.
The Alcator C-Mod facility at the Massachusetts Institute of Technology operated in FY 2016 to complete student researchand experimental work and ceased operations at the end of that fiscal year. The facility was placed in a safe shutdown state
in FY 2017.
The Enabling Research and Development (R&D) element develops the technology to enhance the capabilities for existingand next-generation fusion research facilities, enabling these facilities to achieve higher levels of performance and flexibility
needed to explore new science regimes.
Small-scale tokamak plasma research projects provide data in regimes of relevance to the FES mainline tokamak magnetic
confinement efforts and help confirm theoretical models and simulation codes in support of the FES goal to develop an
experimentally validated predictive capability for magnetically confined fusion plasmas. This activity consists of small-scale
focused experiments.
Spherical Tokamak
The NSTX-U user facility at PPPL is designed to explore the physics of plasmas confined in a spherical torus (ST)
configuration. With its unusually strong magnetic curvature, powerful heating systems, and advanced diagnostics, NSTX-U
will uniquely enable the detailed study of plasmas at ratios of plasma pressure to the pressure of the confining magnetic
field, or plasma beta, many times higher than are accessible in the world’s other tokamaks. The implications of a successful
NSTX-U research program are therefore significant: high plasma pressures translate to high fusion reactivity, making the
NSTX-U geometry a candidate for a future neutron source for scientific study of fusion materials and components. Also, thehigh beta plasmas and measurement capabilities on NSTX-U will enable first-of-a-kind detailed laboratory study of plasma
processes that are relevant to extraordinary astrophysical systems, such as the turbulence in accretion discs surrounding
black holes. The upgraded neutral beam heating systems will combine with the plasma properties to make NSTX-U and
ideal test bed for studying interactions between plasma waves and fast fuel ions that are relevant to burning plasma
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science. The liquid metal divertor research program planned for NSTX-U also will enable assessment of a potential breakout path for fusion heat and particle exhaust handling.
Following an extensive series of reviews (e.g. design validation and verification, extent of condition) in FY 2017, NSTX-U
activities will focus on recovery efforts to repair or replace essential components during FY 2018-19.
Small-scale spherical torus plasma research projects doing focused experiments provide data in regimes of relevance to the
FES spherical torus magnetic confinement program. This effort helps confirm theoretical models and simulation codes insupport of the FES goal to develop an experimentally-validated predictive capability for magnetically confined fusion
plasmas. It also involves high-risk, but high-payoff, experimental efforts useful to advancing spherical torus science.
Theory and Simulation
The Theory and Simulation element contributes to the FES goal of developing the predictive capability needed for asustainable fusion energy source. This element includes two main interrelated but distinct activities: the Theory activity andthe SciDAC activity.
The Theory activity is focused on advancing the scientific understanding of the fundamental physical processes governing
the behavior of magnetically confined plasmas. The efforts supported by this activity range from small single-investigator
grants, mainly at universities, to large coordinated teams at national laboratories, universities, and private industry, while
the supported research ranges from fundamental analytic theory to mid- and large-scale computational work using highperformance computing resources. In addition to its scientific discovery mission, the Theory activity provides the scientificgrounding for the physics models implemented in the advanced simulation codes developed under the SciDAC activity
described below and supports validation efforts at major experiments.
The FES SciDAC activity, a component of the SC-wide SciDAC program, is aimed at advancing scientific discovery in fusion
plasma science by exploiting leadership-class computing resources and associated advances in computational science.
Massively parallel computing, grounded in experimentally validated theoretical models, will be extremely valuable forenabling whole-device modeling that can integrate simulations of physics phenomena across a wide range of disparate timeand space scales. The eight multi-institutional and interdisciplinary centers in the FES SciDAC portfolio address challenges inmagnetic confinement science and computational fusion materials science and are well-aligned with the research needs inburning plasma science. Most of the FES SciDAC portfolio, in partnership with ASCR is up for recompetition in FY 2017. The
portfolio that will emerge from this competition will address the leading-priority research directions identified in the 2015
community workshops.
GPE/GPP/Infrastructure
Funding will support repairs of critical general infrastructure (e.g., utilities, roofs, roads, facilities) at the PPPL site. This
funding level will assure appropriate maintenance of safety requirements, equipment reliability, and research-related
infrastructure needs.

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Fusion Energy Sciences
Burning Plasma Science: Foundations
Activities and Explanation of Changes
FY 2016 Enacted

FY 2018 Request

Advanced Tokamak $101,754,000
DIII-D Research ($34,643,000)
DIII-D Operations ($44,764,000)
Operations funding supported seventeen weeks ofresearch operations at the DIII-D facility, withexperiments focusing on high-priority advanced
tokamak issues and research needs as identified by
the 2015 community workshops. Areas of research
included studies of transport and radiative processes
in detached divertor conditions, disruption physics andmitigation systems, and stability control strategies forrobust high performance operation. Targetedenhancements to the facility involved installation of aset of high-Z coated tile rings in the divertor region to
study impurity generation and transport installation ofa new magnet power supply for the 3D and shaping
coils, and a low-power helicon antenna.

$86,000,000
DIII-D Research ($38,000,000)
DIII-D Operations ($45,000,000)
Operations funding will support eighteen weeks ofresearch at the DIII-D facility. Research will focus on
determining the optimal path to steady-state tokamak
plasmas, exploring techniques to avoid and mitigatetransients in tokamaks, and developing the plasma
material interaction boundary solutions necessary for
future devices. Experiments will continue to exploit a
new upper divertor configuration and explore plasma
wall coupling and dissipative divertor physics. Specificresearch goals will involve examining the processes
that determine the edge pedestal density structure,assessing models of runaway electron evolution
during disruptions, and utilizing new diagnostics toprobe the divertor and edge region to challenge andvalidate theoretical models.

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Explanation of Change
FY 2018 vs FY 2016-$15,754,000+$3,357,000+$236,000
Funding will allow for greater involvement of
university and laboratory collaborators in the DIII-D
national program, including the MIT staff previously
involved in Alcator C-Mod research, as well as NSTXU scientists.

FY 2018 Congressional Budget Justification

FY 2016 Enacted
C-Mod Research ($9,374,000)
C-Mod Operations ($8,675,000)
Operations funding supported over seventeen weeks
of research operations at the Alcator C-Mod facility inits final year of operation in FY 2016. Research was
focused on research needs as identified by the FY
2015 community workshops. Experiments wereconducted to study disruption physics and mitigation
techniques, develop the database for the criticalinteractions between the plasma and material
components under ITER and reactor-relevant
conditions, explore robust high-performancestationary regimes free of Edge Localized Modes, andadvance radiofrequency heating and current drive
technology and physics understanding. The facility wasclosed after final operations. The scientific staff
worked on completing analysis of existing C-Mod data
and began making a transition to collaborative
research activities on other research facilities.
Enabling R&D ($3,165,000)
Support continued to be provided for research insuperconducting magnet technology and fueling andplasma heating technologies to enhance theperformance for existing and future magnetic
confinement fusion devices.
Small-scale Experimental Research ($1,133,000)
Small-scale tokamak plasma research provided
experimental data in regimes of relevance to themainline advanced tokamak magnetic confinement
efforts and helped confirm theoretical models andsimulation codes in support of the goal to develop an
experimentally validated predictive capability formagnetically confined fusion plasmas.

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FY 2018 Request

Explanation of Change
FY 2018 vs FY 2016

C-Mod Research ($0)
C-Mod Operations ($0)
This facility was closed in FY 2016.

-$9,374,000-$8,675,000

Enabling R&D ($2,000,000)
Support will continue to be provided for research insuperconducting magnet technology and plasma
fueling and heating technologies required to enhance
the performance for existing and future magnetic
confinement fusion devices.
Small-scale Experimental Research ($1,000,000)
Support will continue to be provided for research on
experimental data in regimes relevant to mainline
tokamak confinement and experimental validation ofmodels and codes.

-$1,165,000
Research efforts will be focused on the highestpriority enabling R&D issues.

150-$133,000
Experimental research and modeling efforts will be
continued.

FY 2018 Congressional Budget Justification

FY 2016 Enacted

FY 2018 Request

Spherical Tokamak $76,195,000
NSTX-U Research ($27,860,000)
NSTX-U Operations ($44,708,000)
NSTX-U began operations after completion of the
upgrade. Machine performance was extended tohigher field and current and longer pulse lengths thanwhat had been achievable prior to the upgrade, withresults being benchmarked with prior data. Current
drive and fast ion instabilities resulting from the newneutral beam line were studied. The machine
operated for 10 weeks in FY 2016 before experiencing
a coil failure.

$59,100,000
NSTX-U Research ($20,000,000)
NSTX-U Operations ($35,600,000)
Operations funding will support the repair of the
NSTX-U facility. Research will be focused on the studyof ST confinement improvements observed during the
FY 2016 experimental run campaign. Modeling andnew measurements will allow elucidation of thedetailed physical mechanisms responsible for these
confinement improvements. In the absence of plasma
operations at the NSTX-U facility, researchers will carryout experiments on both domestic and international
spherical tokamaks, and continue analysis andpublication of data obtained in FY 2016.

Small-scale Experimental Research ($3,627,000)
Small-scale spherical torus plasma research provided
experimental data in regimes of relevance to themainline spherical torus magnetic confinement efforts
and helped confirm theoretical models and simulation
codes in support of the goal to develop an
experimentally validated predictive capability formagnetically confined fusion plasmas.

Small-scale Experimental Research ($3,500,000)
Experimental studies of plasmas surrounded by liquid
lithium material surfaces, which was identified as apriority research direction in the 2015 plasma
materials interactions workshop, will be conducted.
Developing techniques to operate STs without the useof a central solenoid will be experimentally tested. If
successful, these small-scale, high-risk lines ofresearch may provide underlying scientific insights for
future devices.
$32,500,000
Theory ($15,500,000)
The program will continue to support theoretical andcomputational research addressing fundamental
questions of magnetic confinement science. Emphasis
will be placed on projects maximizing synergy with the
FES SciDAC portfolio and addressing theTheory & Simulation $33,810,000
Theory ($24,439,000)
The program continued to advance the scientificunderstanding of the fundamental physical processes
governing the behavior of magnetically confinedplasmas. Emphasis on addressing ITER priorities

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Explanation of Change
FY 2018 vs FY 2016-$17,095,000-$7,860,000-$9,108,000
The NSTX-U Research funds will support continued
analysis of high-impact data acquired during the FY
2016 run campaign and a focused effort on physics
topics that directly support the recovery of robust
NSTX-U plasma operations. Researchers will alsocollaborate on other spherical tokamak facilities toadvance high-priority research needs that wereidentified by the 2015 community workshops. The
NSTX-U Operations budget supports high-priority
activities to implement repairs and corrective actions
required to obtain robust, reliable research
operations. While consumable expenditures are
reduced due to the non-operation of NSTX-U in FY
2018, the additional anticipated costs associated withthe repair and replacement of components (e.g.,material procurements) offset these savings.
-$127,000
Funding will support experimental research efforts on
small scale spherical tokamak facilities in support of
NSTX-U program priorities.

-$1,310,000-$8,939,000
The program will be refocused to emphasize SciDAC
activities.

FY 2018 Congressional Budget Justification

Explanation of Change
FY 2018 vs FY 2016

FY 2016 Enacted

FY 2018 Request

continued to guide the selection of new and renewal
awards via competitive merit reviews.
SciDAC ($9,371,000)
The five SciDAC centers entered the final year of theirresearch activities, while the three FES–ASCR SciDAC-3
partnerships continued their efforts in the areas ofboundary physics, materials science, and multiscale
integrated modeling. FES and ASCR developed a planemphasizing integration for the science areas
represented by the entire FES SciDAC portfolio andinitiated preparations for a competitive merit review.
GPE/GPP/Infrastructure $5,875,000
Continued support of NSTX-U operations, as well as
enhanced International Collaborations, was provided
through improvements to the Princeton Plasma
Physics Laboratory Computer Center (PPPLCC) andestablishment of remote collaboration room
configurations. Environmental monitoring needs at
PPPL continued to be supported.

recommendations from the 2015 community
workshops.
SciDAC ($17,000,000)
The entire FES SciDAC portfolio will continue to focus
on integrated simulations and whole device modeling,
addressing the leading priority research directions
identified in the 2015 community workshops. Synergy
with whole-device modeling activities supported by
the DOE Exascale Computing Project will bestrengthened.

+$7,629,000
Increase in funding will enable the development andimplementation of additional critical computational
modules, accelerating the development of the wholedevice modeling capability. It will also allow thecontinuation and strengthening of efforts in thecritical area of runaway electron avoidance andmitigation.

$0
All GPE/GPP funding is deferred.

-$5,875,000
All GPE/GPP funding is deferred.

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Fusion Energy Sciences
Burning Plasma Science: Long Pulse
Description
The Burning Plasma Science: Long Pulse subprogram explores new and unique scientific regimes that can be achieved withlong-duration superconducting international machines, and addresses the development of the materials and technologies
required to withstand and sustain a burning plasma. The key objectives of this area are to utilize these new capabilities toaccelerate our scientific understanding of how to control and operate a burning plasma, as well as to develop the basis for a
future fusion nuclear science facility. This subprogram includes long-pulse international tokamak and stellarator research
and fusion nuclear science and materials research.
Long Pulse: Tokamak
Multi-institutional U.S. research teams will continue their successful work on advancing the physics and technology basis forlong-pulse burning plasma operation via bilateral research on U.S. and international fusion facilities. Research on overseas
superconducting tokamaks, conducted onsite and also via fully remote facility operation, leverages progress made indomestic devices and allows the U.S. fusion program to gain the knowledge needed to operate long-duration plasma
discharges in future fusion energy devices. When advantageous, these efforts will be augmented by research into longpulse related physics issues on overseas tokamaks and spherical tokamaks with nonsuperconducting coil systems.
Long Pulse: Stellarator
Stellarators offer the promise of steady-state confinement regimes without transient events such as harmful disruptions.
The three-dimensional (3-D) shaping of the plasma in a stellarator provides for a broader range in design flexibility than isachievable in a 2-D system. The participation of U.S. researchers on W7-X in Germany provides an opportunity to develop
and assess 3-D divertor configurations for long-pulse, high-performance stellarators. The U.S. plans to develop control
schemes to maintain plasmas with stable operational boundaries, including the challenges of control with superconducting
coils and issues of the diagnosis-control cycle in long-pulse conditions. U.S. researchers will play key roles in developing theoperational scenarios and hardware configuration for high-power, steady-state operation, an accomplishment that will
advance the performance/pulse length frontier for fusion. The U.S. contributions during the W7-X construction phase haveearned the U.S. formal partnership status. Accordingly, the U.S. is participating fully in W7-X research and access to data.
The U.S. domestic stellarator program is focused on optimization of the stellarator concept through quasi-symmetricshaping of the toroidal magnetic field. A conventional stellarator lacks axial symmetry, resulting in reduced confinement ofenergetic ions, which are needed to heat the plasma. Quasi-symmetric shaping, invented in the U.S., provides an improved
solution for stable, well confined, steady-state stellarator plasma confinement.
Materials and Fusion Nuclear Science
The fusion environment is extremely harsh in terms of temperature, particle flux, and neutron irradiation. The Materials andFusion Nuclear Science element supports the development, characterization, and modeling of structural, plasma-facing, andblanket materials for use in future fusion devices. Materials that can withstand this environment, under the long-pulse or
steady-state conditions anticipated in fusion experiments, are a prerequisite to the future of fusion research anddevelopment activities. Studies that help identify the various scientific challenges to fusion energy deployment and that
determine how to address them in a safe and environmentally responsible manner are a key component of the Materials
and Fusion Nuclear Science element.

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FY 2018 Congressional Budget Justification

Fusion Energy Sciences
Burning Plasma Science: Long Pulse
Activities and Explanation of Changes
FY 2016 Enacted

FY 2018 Request

Long Pulse: Tokamak $8,944,000
U.S. scientists have developed, installed, andcommissioned improved plasma control feedback
systems for China’s Experimental Advanced
Superconducting Tokamak (EAST) and Korea’s
Superconducting Tokamak Advanced Research(KSTAR). ITER operating scenarios were explored andevaluated on EAST and KSTAR. Radio-frequency
heating and current drive and neutral beam
injection actuator models for EAST and KSTAR weredeveloped and validated.
Long Pulse: Stellarators $7,079,000
Superconducting Stellarator Research ($4,168,000)
U.S. scientists participated in the first plasma
operating campaign of W7-X. The U.S. team wasinvolved with characterizing the 3-D magnetic
configuration and performing the first tests of U.S.supplied equipment during plasma operation. The
team also prepared the Test Divertor Unit (TDU)
scraper element for the second operating campaign.

$8,500,000
Three multi-institutional collaborative teams willcontinue their activities on the superconducting
tokamaks, EAST and KSTAR, focusing on the highpriority areas of control and extension of steadystate plasma scenarios to long-pulse, disruption
physics, and control of plasma-material interfaces
for long-pulse. Research efforts on international
conventional tokamaks will continue to address
burning plasma physics issues relevant to achieving
long pulse plasma operation.
$7,000,000
Superconducting Stellarator Research ($4,500,000)
U.S. research teams will utilize new W7-X
capabilities to enhance the scientific output of thefirst major experimental campaign. Experiments will
investigate controlling the interface between themagnetic field and plasma-facing components,
provide measurements of temperature and poloidal
rotation profiles, and use a stellarator- optimization
code for plasma equilibrium reconstruction fromexperimental measurements.
Compact Stellarator Research ($2,911,000)
Compact Stellarator Research ($2,500,000)
Compact stellarator research provided experimental Research will continue on experiments that aredata in regimes of relevance to the mainline
providing data in regimes relevant to mainline
stellarator magnetic confinement efforts and helped stellarator confinement and experimental validation
confirm theoretical models and simulation codes in of models and codes.
support of the goal to develop an experimentally
validated predictive capability for magneticallyconfined fusion plasmas.

Science/Fusion Energy Sciences154

Explanation of Change
FY 2018 vs FY 2016-$444,000
Funding will continue support for U.S. scientists onsuperconducting tokamaks with unique, world-leading
capabilities, as well as research on international
conventional tokamaks.

-$79,000+$332,000
Funding will enable U.S. scientists to take advantage of
U.S. hardware investments to investigate important
physics issues in long-pulse plasma confinement, suchas edge and impurity transport and pellet fueling forsteady-state operation. Gas puff and phase contrast
imaging studies will be extended.

-$411,000
Research efforts will be focused on the highest-priority
stellarator issues.

FY 2018 Congressional Budget Justification

FY 2016 Enacted

FY 2018 Request

Materials & Fusion Nuclear Science $24,053,000
Fusion Nuclear Science ($11,271,000)
The focus remained on the utilization of existing
experimental capabilities to conduct research in theareas of plasma-facing materials and plasmamaterial interactions consistent with the highpriority research needs identified by the FY 2015
community workshops. Research toward
understanding tritium retention and permeation,neutronics, and material-corrosion issues forblankets continued. Scoping studies continued on
characterizing significant research gaps in thematerials and fusion nuclear sciences program.
Materials Research ($12,782,000)
The focus remained on the utilization of existing
experimental capabilities to conduct research in thearea of material response to simulated fusion
neutron irradiation consistent with the high-priority
research needs identified by the FY 2015 community
workshops. Research toward structural materials
that can withstand high levels of damage, increasing
the ductility of tungsten, and modeling of helium
damage in numerous materials continues.

$19,823,000
Fusion Nuclear Science ($8,823,000)
Research will continue in the areas of plasma-facing
components, safety, tritium fuel cycle, and breeder
blanket technologies. The program will continue toutilize existing facilities in support of foundational
science as emphasized by the 2015 community
workshops and the FES strategic plan. Additionally,
the program will continue to evaluate the potential
for high-priority research on liquid metal plasmafacing components through a systems-level study.

Science/Fusion Energy Sciences

Explanation of Change
FY 2018 vs FY 2016-$4,230,000-$2,448,000
Research efforts will be focused on the highest-priority
fusion nuclear science issues.

Materials Research ($11,000,000)-$1,782,000
Research efforts will continue to emphasize the
Research efforts will be focuses on the highest-priority
utilization of existing experimental capabilities, as
fusion material science issues.
well as explore opportunities for developing newones, to conduct research in the area of fusionmaterial science. The research effort will continue
to focus on the development of materials that canwithstand long term exposure to unprecedented
fluxes of high-energy neutrons and particles, intensethermomechanical stresses, and novel, hightemperatures coolants.

155

FY 2018 Congressional Budget Justification

156

Fusion Energy Sciences
Discovery Plasma Science

Description
The Discovery Plasma Science subprogram supports research that explores the fundamental properties and complex
behavior of matter in the plasma state to improve the understanding required to control and manipulate plasmas for abroad range of applications. Plasma science is not only fundamental to understanding the nature of visible matter
throughout the universe, but also to achieving the eventual production and control of fusion energy. Discoveries in plasma
science are leading to an ever-increasing array of practical applications, such as energy efficient lighting, sterilization andimproved wound healing, combustion enhancement, and carbon storage.
This subprogram supports a portfolio of research projects and small- and mid-scale experimental user facilities for exploring
the diverse frontiers of plasma science. The activities of this subprogram are carried out through inter- and intra-agency
partnerships at academic institutions, industry research groups, and national laboratories across the country.
The Discovery Plasma Science subprogram is organized into two principal activities: Plasma Science Frontiers andMeasurement Innovation.
Plasma Science Frontiers
The Plasma Science Frontiers activities involve research in largely unexplored areas of plasma science, with a combinationof theory, computer modeling, and experimentation. These frontiers are often, but not limited to, the extremes of theplasma state, ranging from the very small (several atom systems) to the extremely large (plasma structure spanning lightyears in length), from the very fast (attosecond processes) to the very slow (hours), from the diffuse (interstellar medium)to the extremely dense (diamond compressed to tens of gigabar pressures), and from the ultra-cold (tens of micro kelvin) tothe extremely hot (stellar core). Advancing the science of these unexplored areas creates opportunities for new andunexpected discoveries with potential to be translated into practical applications.
The Plasma Science Frontiers portfolio includes coordinated research activities in the following three areas:General Plasma Science – Research in frontier areas of basic and low temperature plasma science and engineering,
including advancing our understanding of the behavior of non-neutral and single-component plasmas, ultra-cold
plasmas, dusty plasmas, and micro-plasmas, as well as the study of dynamical processes in classical plasmas
including turbulence, thermal, radiative and particle transport, waves, structures, flows and their interactions.

High Energy Density Laboratory Plasmas – Research directed at exploring the behavior of matter at extreme
conditions of temperature, density, and pressure, including laboratory astrophysics and planetary science,
structure and dynamic of matter at the atomic scale, laser-plasma interactions and relativistic optics, magneto
hydrodynamics (MHD) and magnetized plasmas, and plasma atomic physics and radiation transport.



Exploratory Magnetized Plasma – Basic and applied research directed at developing the understanding oflaboratory magnetized-plasma behavior necessary to advance innovative solutions and capabilities for thecreation, control, and manipulation of magnetically confined plasmas for terrestrial and space applications.

This subprogram stewards world-class, laboratory-based plasma science experiments and user facilities at small andintermediate scales. These platforms not only facilitate addressing frontier plasma science questions but also provide
critical data for the verification and validation of plasma science codes. This effort maintains strong partnerships with the
NSF and NNSA.
Measurement Innovation
The Measurement Innovation activity supports the development of novel and innovative diagnostic techniques and theirapplication to new, unexplored, or unfamiliar plasma regimes or scenarios. The challenge is to develop diagnostics with thespatial, spectral, and temporal resolution necessary to validate plasma physics models used to predict the behavior of
fusion plasmas. Advanced diagnostic capabilities successfully developed through this activity are migrated to domestic andinternational facilities, as part of the Burning Plasma Science: Foundations and Burning Plasma: Long Pulse subprograms.
The implementation of mature diagnostics systems is supported via the research programs at FES user facilities.
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FY 2018 Congressional Budget Justification

SBIR/STTR & Other
Funding for SBIR/STTR is included in this subprogram. Other activities that are supported include research at HistoricallyBlack Colleges and Universities (HBCUs); the U.S. Burning Plasma Organization (USBPO), a national organization thatcoordinates research in burning plasma science; peer reviews for solicitations across the program; and FESAC.

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FY 2018 Congressional Budget Justification

Fusion Energy Sciences
Discovery Plasma Science
Activities and Explanation of Changes
Explanation of Change
FY 2018 vs FY 2016

FY 2016 Enacted

FY 2018 Request

Plasma Science Frontiers $46,504,000
General Plasma Science ($14,196,000)
Research continued in fundamental science areas ofplasma turbulence and transport, interactions ofplasmas and waves, statistical mechanics of plasmas,
and self-organization and reconnection. Research on
major FES user facilities was enhanced.
High Energy Density Laboratory Plasmas($21,495,000)
Research emphasized utilizing the Matter in Extreme
Conditions (MEC) instrument at the LCLS facility,
including continued operational support for the MEC
instrument and the HEDLP research group at SLAC as
well as grants for external HED science users of MEC.
Fundamental HEDLP science was supported throughnew research grants as part of the SC/NNSA Joint
Program in HEDLP and the NSF/DOE Partnership in
Basic Plasma Science and Engineering, as well as
operation of the Neutralized Drift Compression
Experiment-II.
Exploratory Magnetized Plasma ($10,813,000)
This portfolio was evaluated through a competitive
peer-review process.

$23,600,000
General Plasma Science ($12,750,000)
Core research areas of this activity will continue witha program focus on intermediate-scale, plasma
science user facilities, as well as research in areas
identified in the 2015 Frontiers of Plasma Science
Workshops Report.
High Energy Density Laboratory Plasmas ($6,850,000)-$22,904,000-$1,446,000
Research and operations on intermediate-scale user
facilities will be emphasized to pursue opportunities
identified in the 2015 community workshops.

Research will emphasize utilizing the MEC at LCLS,
including continued support for the MEC beam-linescience team and the experimental and theoretical
HEDP research groups at SLAC.

Support will be focused on research and operations
for the MEC.

Exploratory Magnetized Plasma ($4,000,000)
Research efforts will focus on discovery at the frontierof laboratory magnetized-plasma physics,
emphasizing research in areas identified in the 2015
community workshops.

-$6,813,000
Research and operations on intermediate-scale user
facilities will be emphasized to pursue opportunities
identified in the 2015 community workshops.

Science/Fusion Energy Sciences

159-$14,645,000

FY 2018 Congressional Budget Justification

FY 2016 Enacted

FY 2018 Request

Measurement Innovation $3,568,000Core research elements of the Measurement
Innovation activity continued with enhanced effort ondiagnostic development important to addressing thescientific issues identified in the community
workshops held in FY 2015.
SBIR/STTR & Other $15,218,000
Funding continued to support USBPO activities,
HBCUs, peer reviews for solicitations, and FESAC.
SBIR/STTR funding is statutorily set at 3.45 percent of
noncapital funding in FY 2016.

$900,000
Measurement Innovation research activities willcontinue with special emphasis on diagnostics forplasma transient instabilities, plasma-materials
interactions, modeling validation, and basic plasma
science identified in the 2015 community workshops.
$9,517,000
Funding will continue to support USBPO activities,
HBCUs, peer reviews for solicitations, and FESAC.
SBIR/STTR funding is statutorily set at 3.45 percent of
noncapital funding in FY 2018.

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160

Explanation of Change
FY 2018 vs FY 2016-$2,668,000
Funding will support activities initiated through the FY
2017 measurement innovation solicitation.

-$5,701,000
Funding supports SBIR/STTR and other activities.

FY 2018 Congressional Budget Justification

Fusion Energy Sciences
Construction
Description
The ITER facility, currently under construction in St. Paul-lez-Durance, France, aims to provide access to burning plasmas with fusion power output approaching reactor
levels of hundreds of megawatts, for hundreds of seconds. Construction of ITER is a collaboration among the United States, European Union, Russia, Japan, India, South
Korea, and China, governed by an international agreement (the “ITER Joint Implementing Agreement”), through which the U.S. contributes in-kind-hardware
components, personnel, and direct monetary funding to the ITER Organization (IO).

Fusion Energy Sciences
Construction
Activities and Explanation of Changes
FY 2016 Enacted
U.S. Contributions to ITER Project $115,000,000
Funding supported continued progress on in-kind
hardware contributions, including: central solenoid
superconducting magnet modules and structures,
toroidal field magnet conductor, steady-stateelectrical network components, and tokamak coolingwater system components.

Science/Fusion Energy Sciences

FY 2018 Request$63,000,000
Funding is provided for ITER.

161

Explanation of Change
FY 2018 vs FY 2016-$52,000,000
Funding is reduced for the ITER project. No funding isprovided for the annual IO monetary contribution for
FY 2018.

FY 2018 Congressional Budget Justification

Fusion Energy Sciences
Performance Measures
In accordance with the GPRA Modernization Act of 2010, the Department sets targets for, and tracks progress toward, achieving performance goals for each program.

Performance Goal
(Measure)
TargetResultEndpoint Target

FY 2016
FY 2017
FY 2018
FES Facility Based Experiments - Experiments conducted on major fusion facilities [DIII-D National Fusion Facility (DIII-D) and National
Spherical Torus Experiment Upgrade (NSTX)-U] leading toward predictive capability for burning plasmas and configuration optimization
Conduct research to detect and minimize the Conduct research to examine the effect ofConduct research to test predictive models ofconsequences of disruptions in present andconfiguration on operating space for dissipative fast ion transport by multiple Alfvén
divertors. Handling plasma power and particle eigenmodes. Fusion alphas and injected
future tokamaks. Coordinated research will
exhaust in the divertor region is a critical issue energetic neutral particle beams provide an
deploy a disruption prediction/warning
for future burning plasma devices. The veryalgorithm on existing tokamaks, assess
important source of heating and current drive
approaches to avoid disruptions, and quantify narrow edge power exhaust channel projected in advanced tokamak operating scenarios andfor tokamak devices that operate at highplasma and radiation asymmetries resulting
burning plasma regimes. Alfvén eigenmodefrom disruption mitigation measures, including poloidal magnetic field is of particular concern. instabilities can cause the redistribution or loss
both preexisting and resulting MHD activity, as Increased and controlled divertor radiation,of fast ions and driven currents, as well as
potentially decreasing fusion performance andwell as the localized nature of the disruption coupled with optimization of the divertor
leading to localized losses. Measured fast ion
mitigation system. The research will employ configuration, are envisioned as the leading
approaches to reducing peak heat flux on the fluxes in DIII-D and NSTX-U plasmas withnew disruption mitigation systems, control
divertor targets and increasing the operating
different levels of Alfvén eigenmode activity
algorithms, and hardware to help avoid
window for dissipative divertors. Data obtained will be used to determine the threshold for
disruptions, along with measurements tosignificant fast ion transport, assess
detect disruption precursors and quantify the from DIII-D and NSTX-U and archived from
Alcator C-Mod will be used to assess the impact mechanisms and models for such transport,
effects of disruptions.
of edge magnetic configurations and divertor and quantify the impact on beam power
geometries on dissipative regimes, as well as
deposition and current drive. Measurements
their effect on the width of the power exhaust will be compared with theoretical predictions,channel, thus providing essential data to test
including quantitative fluctuation data and fastand validate leading boundary plasma models. ion density, in order to validate models andimprove understanding of underlying
mechanisms. Model predictions will guide thedevelopment of attractive operating regimes.
Met
TBD
TBD
Magnetic fields are the principal means of confining the hot ionized gas of a plasma long enough to make practical fusion energy. The detailed
shape of these magnetic containers leads to many variations in how the plasma pressure is sustained within the magnetic bottle and the degreeof control that experimenters can exercise over the plasma stability. These factors, in turn, influence the functional and economic credibility of

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FY 2018 Congressional Budget Justification

Performance Goal
(Measure)

the eventual realization of a fusion power reactor. The key to their success is a detailed physics understanding of the confinement
characteristics of the plasmas in these magnetic configurations. The major fusion facilities can produce plasmas that provide a wide range ofmagnetic fields, plasma currents, and plasma shapes. By using a variety of plasma control tools, appropriate materials, and having thediagnostics needed to measure critical physics parameters, scientists will be able to develop optimum scenarios for achieving high performance
plasmas in future burning plasma devices and, ultimately, in power plants.
FES Facility Operations - Average achieved operation time of FES user facilities as a percentage of total scheduled annual operation timeTargetResultEndpoint Target

Performance Goal
(Measure)
TargetResultEndpoint Target≥ 90 %≥ 90 %≥ 90 %Met
TBD
TBD
Many of the research projects that are undertaken at the Office of Science’s scientific user facilities take a great deal of time, money, and effort
to prepare and regularly have a very short window of opportunity to run. If the facility is not operating as expected the experiment could beruined or critically setback. In addition, taxpayers have invested millions or even hundreds of millions of dollars in these facilities. The greater
the period of reliable operations, the greater the return on the taxpayers’ investment.
FES Theory and Simulation - Performance of simulations with high physics fidelity codes to address and resolve critical challenges in theplasma science of magnetic confinement
Predicting the magnitude and scaling of theLower hybrid current drive (LHCD) will be
The interaction of the boundary plasma withdivertor heat load width in magneticallyindispensable for driving off-axis current during the material surfaces in magnetically confined
confined burning plasmas is a high priority for long-pulse operation of future burning plasma plasmas is among the most critical problems in
the fusion program. One of the key unresolved experiments, since it offers important leverage fusion energy science. In FY 2018, perform
physics issues is what sets the heat flux width for controlling damaging transients caused by high-performance computational simulations
at the entrance to the divertor region. Perform magnetohydrodynamic instabilities. However, with coupled boundary plasma physics andthe experimentally demonstrated highmassively parallel simulations using 3D edge
materials surface models to predict the fuelefficiency of LHCD is incompletely understood. recycling and tritium retention of the divertor
kinetic and fluid codes to determine theparameter dependence of the heat load width In FY 2017, massively parallel, high-resolution for deuterium-tritium burning plasma
simulations with 480 radial elements and 4095 conditions, accounting for erosion, reat the divertor entrance and compute thedivertor plate heat flux applicable to moderate poloidal modes will be performed using fulldeposition and impurity transport in theparticle recycling conditions. Comparisons will wave radiofrequency field solvers and particle plasma boundary, and an initial evaluation of
be made with data from DIIID, NSTX-U, and C- Fokker-Planck codes to elucidate the roles of
the influence of material deposition on thetoroidicity and full-wave effects. The simulation recycling and retention.
Mod.
predictions will be compared with experimental
data from the superconducting EAST tokamak.
Met
TBD
TBD
Advanced simulations based on high physics fidelity models offer the promise of advancing scientific discovery in the plasma science ofmagnetic fusion by exploiting the Office of Science high performance computing resources and associated advances in computational science.
These simulations are able to address the multiphysics and multiscale challenges of the burning plasma state and contribute to the FES goal ofadvancing the fundamental science of magnetically confined plasmas to develop the predictive capability needed for a sustainable fusionenergy source.

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FY 2018 Congressional Budget Justification

Fusion Energy Sciences
Capital Summary ($K)
Total

Prior Years

FY 2016
Enacted

n/a
n/a

n/a
n/a

7,566
5,521

n/a

n/a

13,087-

83,66580,1950Total MIEs
Total Non-MIE Capital Equipment
Total, Capital equipment

n/a
n/a
n/a

80,195n/an/aGeneral Plant Projects c
General Plant Projects under $2 million TEC

n/a

n/a

Capital Operating Expenses Summary
Capital equipment
General plant projects (GPP)
Accelerator Improvement Projects (AIP) (<$5M)
Total, Capital Operating Expenses
Capital Equipment
Major items of equipment b
National Spherical Torus Experiment Upgrade (TPC
$94,300)

FY 2017
Annualized CR a

FY 2018
RequestFY 2018 vs
FY 2016

0-7,566-5,5210-13,087

-

0

0

0
7,566
7,566

-

0

0

5,521

-

aFY 2017 Annualized CR amounts reflect the P.L. 114-254 continuing resolution level annualized to a full year. These amounts are shown only at the congressional control level and above,

below that level, a dash (-) is shown.

b Each MIE located at a DOE facility Total Estimated Cost (TEC) >$5M and each MIE not located at a DOE facility TEC > $2M.
c Each Plant Project (GPP/GPE) Total Estimated Cost (TEC) > $5M

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FY 2018 Congressional Budget Justification

Fusion Energy Sciences
Construction Projects Summary ($K)

14-SC-60, U.S. Contributions to ITER Project
Total Estimated Cost (TEC)
Other Project Cost (OPC)
Total, Project Cost (TPC), 14-SC-60

Total

Prior Years

FY 2016
EnactedFY 2017
EnactedFY 2018
RequestFY 2018 vs
FY 2016

TBD
TBD
TBD

947,905
74,9801,022,885

115,0000
115,000

50,00063,000063,000-52,0000-52,000

50,000Fusion Energy Sciences
Funding Summary ($K)

Research
Scientific user facility operations
Major items of equipment
Other (GPP, GPE, and infrastructure)
Construction
Total, Fusion Energy Sciences

FY 2016 Enacted
218,978
98,1470
5,875
115,000
438,000

FY 2017 Annualized CR a
437,167

FY 2018 Request
166,340
80,6000
063,000309,940

FY 2018 vs FY 2016
-52,638-17,547
0-5,875-52,000-128,060

a
FY 2017 Annualized CR amounts reflect the P.L. 114-254 continuing resolution level annualized to a full year. These amounts are shown only at the congressional control
level and above, below that level, a dash (-) is shown.

Science/Fusion Energy Sciences165

FY 2018 Congressional Budget Justification

Scientific User Facility Operations and Research ($K)
The treatment of user facilities is distinguished between two types: TYPE A facilities that offer users resources dependent on a single, large-scale machine; TYPE B
facilities that offer users a suite of resources that is not dependent on a single, large-scale machine.
Definitions:
Achieved Operating Hours – The amount of time (in hours) the facility was available for users.
Planned Operating Hours – For Past Fiscal Year (PY), the amount of time (in hours) the facility was planned to be available for users.
 For Current Fiscal Year (CY), the amount of time (in hours) the facility is planned to be available for users.
 For the Budget Fiscal Year (BY), based on the proposed budget request the amount of time (in hours) the facility is anticipated to be available for users.
Optimal Hours – The amount of time (in hours) a facility would be available to satisfy the needs of the user community if unconstrained by funding levels.
Percent of Optimal Hours – An indication of utilization effectiveness in the context of available funding; it is not a direct indication of scientific or facility productivity.
 For BY and CY, Planned Operating Hours divided by Optimal Hours expressed as a percentage.
 For PY, Achieved Operating Hours divided by Optimal Hours.
Unscheduled Downtime Hours – The amount of time (in hours) the facility was unavailable to users due to unscheduled events. NOTE: For type “A” facilities, zero
Unscheduled Downtime Hours indicates Achieved Operating Hours equals Planned Operating Hours.

TYPE A FACILITIESDIII-D National Fusion Facility
Number of Users
Achieved operating hours
Planned operating hours
Optimal hours
Percent optimal hours
Unscheduled downtime hours

FY 2016 Enacted

FY 2017 Annualized CR a

FY 2018 Request

FY 2018 vs FY 2016

$79,407
618
691
600
1,000
69.1%
0

-

$83,000
650
N/A
720
720
100%
N/A

+$3,593
+32
+120
-280
+31%
N/A

a
FY 2017 Annualized CR amounts reflect the P.L. 114-254 continuing resolution level annualized to a full year. These amounts are shown only at the congressional control
level and above, below that level, a dash (-) is shown.

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FY 2018 Congressional Budget Justification

FY 2016 Enacted

FY 2017 Annualized CR a

FY 2018 Request

FY 2018 vs FY 2016

Alcator C-Mod
Number of Users
Achieved operating hours
Planned operating hours
Optimal hours
Percent optimal hours
Unscheduled downtime hours$18,049
140
N/A
160
800
20%
N/A

-

0
0
N/A
0
0
0
N/A

-$18,049
0
N/A
0
0
0
N/A

National Spherical Torus Experiment-Upgrade
Number of Users
Achieved operating hours
Planned operating hours
Optimal hours
Percent optimal hours
Unscheduled downtime hours$72,568
362
402
720
1,000
40%

-

-$16,968
-65
N/A
-720
-1,000
-40%

318

-

$55,600
297
N/A
0
0
N/A
N/A

Total Facilities
Number of Users
Achieved operating hours
Planned operating hours
Optimal hours
Percent of optimal hoursbab
Unscheduled downtime hours$170,024
1,206
1,650
1,480
2,800
55.9%
318

-

138,600
970
N/A
720
720
100%
N/A

-$31,424
+8
N/A
-760
-1,800+44.1%N/A

N/Aa

FY 2017 Annualized CR amounts reflect the P.L. 114-254 continuing resolution level annualized to a full year. These amounts are shown only at the congressional
control level and above, below that level, a dash (-) is shown.
b

For total facilities only, this is a “funding weighted” calculation FOR ONLY TYPE A facilities:

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167

∑𝑛𝑛
1 [(%𝑂𝑂𝑂𝑂 𝑓𝑓𝑓𝑓𝑓𝑓 𝑓𝑓𝑓𝑓𝑓𝑓𝑓𝑓𝑓𝑓𝑓𝑓𝑓𝑓𝑓𝑓 𝑛𝑛)×(𝑓𝑓𝑓𝑓𝑓𝑓𝑓𝑓𝑓𝑓𝑓𝑓𝑓𝑓 𝑓𝑓𝑓𝑓𝑓𝑓 𝑓𝑓𝑓𝑓𝑓𝑓𝑓𝑓𝑓𝑓𝑓𝑓𝑓𝑓𝑓𝑓 𝑛𝑛 𝑜𝑜𝑜𝑜𝑜𝑜𝑜𝑜𝑜𝑜𝑜𝑜𝑜𝑜𝑜𝑜𝑜𝑜𝑜𝑜)]
𝑇𝑇𝑇𝑇𝑇𝑇𝑇𝑇𝑇𝑇 𝑓𝑓𝑓𝑓𝑓𝑓𝑓𝑓𝑓𝑓𝑓𝑓𝑓𝑓 𝑓𝑓𝑓𝑓𝑓𝑓 𝑎𝑎𝑎𝑎𝑎𝑎 𝑓𝑓𝑓𝑓𝑓𝑓𝑓𝑓𝑓𝑓𝑓𝑓𝑓𝑓𝑓𝑓 𝑜𝑜𝑜𝑜𝑜𝑜𝑜𝑜𝑜𝑜𝑜𝑜𝑜𝑜𝑜𝑜𝑜𝑜𝑜𝑜

FY 2018 Congressional Budget Justification

Scientific Employment

Number of permanent Ph.D.’s (FTEs)
Number of postdoctoral associates (FTEs)
Number of graduate students (FTEs)
Other b

FY 2017 Annualized CR a-

FY 2016 Enacted
767
98
293
1,025

FY 2018 Request
510
65
160
785

FY 2018 vs FY 2016
-253
-33
-133
-240

a

FY 2017 amounts shown reflect the P.L. 114-254 continuing resolution level annualized to a full year. These amounts are shown only at the congressional control level
and above, below that level, a dash (-) is shown.
b
Includes technicians, engineers, computer professionals, and other support staff.
Science/Fusion Energy Sciences168

FY 2018 Congressional Budget Justification

14-SC-60, U.S. Contributions to ITER
1.

Significant Changes and Summary

Significant Changes
This Construction Project Data Sheet (CPDS) is an update of the FY 2017 CPDS and does not include a new start for FY 2018.
The DOE Order 413.3B approved Critical Decision (CD) CD-1, “Approve Alternative Selection and Cost Range” was approvedon January 25, 2008 with a preliminary cost range of $1.45–$2.2 billion. Since 2008, the estimated cost range for the projectincreased such that the upper bound of the approved CD-1 cost range increased by more than 50% triggering the need for areassessment of the project cost range and re-approval by the Project Management Executive (PME). The ProjectManagement Executive for the U.S. ITER project is the Deputy Secretary of Energy. The cost range reassessment wascompleted in November 2016 and it was then subsequently approved by the PME in January 13, 2017. The CD-1 Revised
cost range is now $4.7B to $6.5B.
DOE has divided the U.S. ITER project hardware scope into two distinct subprojects, which represent the two phases of the
project: subproject 1 is the hardware scope leading to First Plasma (FP), and subproject 2 is hardware for the post-First
Plasma project. This CPDS focuses only on the FP subproject activities. A review of CD-2, “Approve Performance Baseline”
for the First Plasma subproject was completed in November 2016 and then subsequently approved by the PME on January
13, 2017, with a total project cost of $2.5B, with a CD-4, “Project Completion” date of December 2027.
The FP subproject scope consists of: 1) completing the design for all twelve subsystems the U.S. was contributing to ITER; 2)complete fabrication and delivery of the Toroidial Field (TF) coil superconductor, Steady State Electrical Network (SSEN), andthe Central Solenoid (CS) superconducting magnet modules and associated structures; and 3) partial fabrication anddelivery of seven other subsystems: Tokamak Cooling Water, Roughing Pumps, Vacuum Auxillary, Pellet Injection, Ion
Cyclotron Heating, Electron Cyclotron Heating, Diagnostics.
Summary
ITER is a major fusion research facility being constructed in St. Paul-lez-Durance, France by an international partnership ofseven governments. Since it will not result in a facility owned by the U.S. or located in the U.S., the U.S. Contributions to
ITER (U.S. ITER) project is not classified as a Capital Asset project, but is classified as a Major System Project. The U.S. ITER
project is a U.S. Department of Energy project to provide the U.S. share of the ITER project (in-kind hardware i.e.,subsystems, equipment, and components, as well as monetary resources to support the ITER Organization (IO) in France).
Sections of this CPDS have been tailored accordingly to reflect the nature of this project.
The U.S. ITER project is managed as a DOE Office of Science (SC) project. The project began as a Major Item of Equipment(MIE) in FY 2006, and was changed to a Congressional control point Line-Item beginning in FY 2014. As with all SC projects,
the principles of DOE Order 413.3B are applied in the effective management of the project, including critical decision
milestones and their supporting prerequisite activities. Requirements for project documentation, monitoring and reporting,change control, and regular independent project reviews are being applied with the same degree of rigor as other SC lineitem projects. Progress and performance are reported regularly in monthly performance metrics and project status reports.
As of the end of September, 2017, the U.S. ITER FP project is more than 50% complete; design of hardware needed for FP
technical systems is 86% complete; and 19% of the hardware deliveries are complete. Active fabrication is underway in fiveof the U.S. twelve hardware systems (TCWS, Steady State Electric Network [SSEN] Components, Toroidal Field [TF]
Conductor and CS Magnets and Vacuum Auxiliary Systems [VAS]). The U.S. has also procured major high-voltage electric
power components (e.g., transformers, switch gear, circuit breakers, and voltage regulators). Deliveries of U.S. electric
power components to the ITER site in France began in FY 2014 and were completed in FY 2017. Fabrication of the TF coilsuperconductor was also competed in FY 2017. The U.S. ITER project has subcontracted with General Atomics (GA) for the
fabrication of the world’s largest pulsed superconducting magnets for the ITER CS magnet system. In FY 2017,
commissioning was completed for all of the eleven work stations in the CS magnet module fabrication facility for the
fabrication of the seven (six production and one spare) magnet modules the U.S. is responsible for delivering to theinternational ITER project. The U.S. completed fabrication of a mockup (non-superconducting) copper coil which was toprovide assurance of all the CS manufacturing processes. Also, GA completed the winding of the first two magnet modules
Science/Fusion Energy Sciences/
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FY 2018 Congressional Budget Justification

in FY 2017. By the end of CY 2017, five of seven modules will be in fabrication. To date the U.S. ITER project has awarded
and obligated over $860 million to U.S. industry, universities, and DOE laboratories.
FY 2018 funding will support ITER Project Office operations including project management. Additional planning will follow
discussions with Congress and ITER partners.
The U.S ITER Federal Project Director with certification level 3 has been assigned to this Project and has approved this CPDS.
2.

Critical Milestone History(fiscal quarter or date)
CD-0

FY 2006
FY 2007
FY 2008
FY 2009
FY 2010
FY 2011
FY 2012FY 2013
FY 2014
FY 2015
FY 2016 k
FY 2017 l

7/5/2005
7/5/2005
7/5/2005
7/5/2005
7/5/2005
7/5/2005
7/5/2005
7/5/2005
7/5/2005
7/5/2005
7/5/2005
7/5/2005

Conceptual
DesignComplete

09/30/2009 a
07/27/2010 b
05/30/2011 c
07/10/2012 e
12/11/2012 g

CD-1

CD-2

TBD
TBD
1/25/2008
1/25/2008
1/25/2008
1/25/2008
1/25/2008
1/25/2008
1/25/2008
1/25/2008
1/25/2008
1/25/2008

TBD
TBD
4Q FY 2008
4Q FY 2010
4Q FY 2011
4Q FY 2011
3Q FY 2012
TBD h
TBD
TBD
TBD
TBD

Final Design
Complete

04/12/2011 d
05/02/2012 f
04/10/2013 i
12/10/2013 j

CD-3

D&D
Complete

CD-4

TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD

N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A

TBD
2017
2017
2018
2019
2024
2028
2033
2034
2036
TBD
TBD

CD-0 – Approve Mission Need
CD-1 – Approve Alternative Selection, Cost Range, and Start of Long-lead Procurements
CD-2 – Approve Performance Baseline
CD-3 – Approve Start of Fabrication
CD-4 – Approve Project CompletionaElectron Cyclotron Heating (ECH) Transmission lines (TL) (06/22/2009); Tokamak Cooling Water System (07/21/2009); CS
Modules, Structures, and Assembly Tooling (AT) (09/30/2009).
b
Ion Cyclotron Heating Transmission Lines (ICH) (10/14/2009); Tokamak Exhaust Processing (TEP) (05/17/2010); Diagnostics:
Residual Gas Analyzer (RGA) (07/14/2010), Upper Visible Infrared Cameras (VIR) (07/27/2010).
c
Vacuum Auxiliary System (VAS) – Main Piping (12/13/2010); Diagnostics Low-Field-Side Reflectometer (LFS) (05/30/2011).
d
Cooling Water Drain Tanks (04/12/2011).
e
Diagnostics: Upper Port (10/03/2011), Electron Cyclotron Emission (ECE) (12/06/2011), Equatorial Port E-9 and Toroidal
Interferometer Polarimeter (TIP) (01/02/2012), Equatorial Port E-3 (07/10/2012).
f
Steady State Electrical Network (05/02/2012).
g
VAS Supply (11/13/2012); Disruption Mitigation (12/11/2012); Pellet Injection (04/29/2013); Diagnostics: Motional Stark
Effect Polarimeter (MSE) (05/29/2013), Core Imaging X-ray Spectrometer (CIXS) (06/01/2013).
h
The CD-2 date will be determined upon acceptable resolution of issues related to development of a high-confidence ITER
Project Schedule and establishment of an approved funding profile.
i
RGA Divertor Sampling Tube (07/28/14); CS AT, Early Items (09/17/14).
j
CS Modules and Structures (11/18/2013); VAS Main Piping B-2, L-1, L-2 (12/10/2013).
k
CS AT Remaining Items (12/02/2015).
l
Roughing Pumps (03/2017); VAS 03 Supply (06/2017); Roughing Pumps I&C (06/2017); VAS 03 Supply I&C (04/2017); CS AT
Bus Bar Alignment and Coaxial Heater (04/2017); VAS Main Piping L3/L4 (03/2017); VAS 02 CGVS (&C Part 1 (06/2017).
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170

FY 2018 a 7/5/2005
3.

CD-1 Cost
Range
Update
1/13/17

CD-2/3SP-1
1/13/17

CD-4
SP-2
2019

SP-1
1Q2027SP-2
2034-2038

Project Cost History

At the time of CD-1 approval in January 2008, the preliminary cost range for the total U.S. ITER project was $1.45–$2.2 billion. Until recently, however, it has not been possible to confidently baseline the project due to past delays in theinternational ITER construction schedule. Various factors (e.g., schedule delays, design and scope changes, funding
constraints, regulatory requirements, risk mitigations, and project management and leadership issues in the ITER
Organization) have affected the project cost. In response to a 2013 Congressional request, a DOE Office of Science IPR
Committee assessed the project and determined that the existing cost range estimate of $4.0 to $6.5B would likely
encompass the final TPC. This range, recommended in 2013, was included in subsequent Budget Requests and in the May
2016 DOE “Report on the Continued U.S. Participation in the ITER Project” to Congress. Following briefings and discussions
with the Secretary’s Project Management Risk Committee, the Undersecretary for Science and Energy, and the Director of
the Office of Science, in preparation for baselining FP, a decision was made to update the lower end of this range to reflect
updated cost estimates resulting in the current approved CD-1R range of $4.7 to 6.5B. This updated CD-1R range
incorporates increases in the projects hardware estimate that have occurred since August 2013. The First Plasma subproject
TPC has been baselined at $2.5B.
4.

Project Scope and Justification

Scope
ITER is an international partnership among seven Member governments (China, the European Union, India, Japan, theRepublic of Korea, the Russian Federation, and the United States) aimed at demonstrating the scientific and technologicalfeasibility of fusion energy for peaceful purposes. The Agreement on the Establishment of the ITER International Fusion
Energy Organization for the Joint Implementation of the ITER Project (ITER Agreement), signed on November 21, 2006,
provides the legal framework for the four phases of the program: construction, operation, deactivation, anddecommissioning. Through participation in the agreement, the European Union, as the host, will bear five-elevenths(45.45%) of the ITER facility’s construction cost, while the other six Members, including the U.S., will each support oneeleventh (9.09%) of the ITER facilities cost. Operation, deactivation, and decommissioning of the facility are to be fundedthrough a different cost-sharing formula in which the U.S. will contribute a 13% share, which is not a part of the U.S. ITER
project funding. Responsibility for ITER integration, management, design, licensing, installation, and operation rests with the
ITER Organization (IO), which is an international legal entity located in France.
Justification
The purpose of ITER is to investigate and conduct research in the so-called “burning plasma” regime—a performance region
that exists beyond the current experimental state of the art. Creating a self-sustaining burning plasma will provide essential
scientific knowledge necessary for practical fusion power. There are two parts of this need that will be achieved by ITER. The
first part is to investigate the fusion process in the form of a "burning plasma," in which the heat generated by the fusion
process exceeds that supplied from external sources (i.e., self-heating). The second part of this need is to sustain theburning plasma for a long duration (e.g., several hundred to a few thousand seconds), during which time equilibrium
conditions can be achieved within the plasma and adjacent structures. ITER is the necessary next step to establish theconfidence in proceeding with development of a demonstration fusion power plant.

a

VAS 02 Supply Part 1 (05/2018); ICH RF Building and I&C (11/2017); TCWS Captive Piping and First Plasma (10/2017); ICH
RF components supporting INDA/IO testing (01/2018).
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171

5.

Financial Schedule(dollars in thousands)
Appropriations
Obligations
Total Estimated Cost (TEC)
Hardware
FY 2006
FY 2007
FY 2008
FY 2009
FY 2010
FY 2011
FY 2012 b
FY 2013
FY 2014 c
FY 2015
FY 2016 d
FY 2017
FY 2018
Subtotal
Total, Hardware
Cash Contributions e
FY 2006
FY 2007
FY 2008
FY 2009
FY 2010
FY 2011
FY 2012FY 2013
FY 2014b
FY 2015
FY 2016 f
FY 2017
FY 2018
Subtotal
Total, Cash Contributions
Total, TEC
Other project costs (OPC)FY 2006
FY 2007
FY 2008
FY 2009
FY 2010a

Costs a13,754
34,58825,50085,401
85,26663,87591,441
107,635
161,605
128,682
115,000
50,00063,0001,025,747
TBD

13,754
34,58825,50085,401
85,26663,87591,407
107,669
161,605
128,682
115,000
50,00063,0001,025,747
TBD

6,169
24,23824,122
26,27846,052
84,321
99,215110,074
153,368
105,908
102,561
158,942
73,0001,014,248
TBD

2,112
7,412
2,644
23,59929,734
3,125
13,214
13,80532,895
15,95700
0144,497
TBD
TBD

2,112
7,412
2,644
23,59929,734
3,125
13,214
13,80532,895
15,95700
0144,497
TBD
TBD

2,112
7,412
2,644
23,59929,734
3,125
13,214
13,80532,895
15,95700
0144,497
TBD
TBD

3,449
18,000-2,07415,00020,0003,449
18,000-2,07415,00020,000

1,110
7,607
7,513
5,072
7,754

Costs through FY 2016 reflect actual costs; costs for FY 2017 and the outyears are estimates.
Prior actuals adjusted to incorporate project funds utilized at PPPL and DOE. Obligation adjusted to reflect year-end PPPL
settlement funding.
cAppropriations prior to FY 2014 reflect major item of equipment funding. Starting in FY 2014, this project is funded as a
Congressional control point.
d
FY 2016 funding for taxes and tax support is included in the FY 2017 Hardware funding amount.
eIncludes cash payments, secondees, taxes and tax support.
f
No FY 2016 funding is provided to support the ITER organization.
Science/Fusion Energy Sciences/
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FY 2018 Congressional Budget Justification172b

(dollars in thousands)
Appropriations
Obligations
13,00013,000
345
345
2,560
2,560
5,000
5,000
5,361
5,361
0
0
0
0
0
0
80,64180,641TBD
TBD

FY 2011
FY 2012 a
FY 2013
FY 2014 b
FY 2015
FY 2016
FY 2017
FY 2018
Subtotal
Total, OPC
Total Project Costs (TPC)FY 2006
FY 2007
FY 2008
FY 2009
FY 2010
FY 2011
FY 2012a
FY 2013
FY 2014b
FY 2015
FY 2016
FY 2017
FY 2018
Subtotal
Total, TPC
6.

19,31560,00026,070124,000
135,000
80,000105,000
124,000
199,500
150,000
115,000
50,00063,0001,250,885
TBD

19,31560,00026,070124,000
135,000
80,000104,966
124,034
199,500
150,000
115,000
50,00063,0001,250,885
TBD

Costs a10,032
22,336
5,984
2,717
5,500
3,958
1,058
0
80,641
TBD
9,391
39,25734,27954,94983,54097,478
134,765
129,863
188,980
127,365
106,519
160,000
73,0001,239,386
TBD

Details of the 2018 Project Cost Estimate

An Independent Project Review of U.S. ITER was conducted on November 14-17, 2016, to consider the project’s readinessfor CD-2 (Performance Baseline) and CD-3 (Begin / Continue Fabrication) for FP as well as the proposed updated CD-1 Cost
Range. Outcomes from the IPR indicated that the project was ready for approval of FP CD-2/3 following a reassessment ofcontingency to account for risk in the areas of escalation and currency exchange. This recommendation has been addressed.
7.

Schedule of Appropriation Requests

FY 2006

FT 2007

a

TEC
OPC
TPC
TEC
OPC
TPC

Prior
Years
1,009,00
080,6001,089,60
0930,151
44,949975,100

FY 2013
29,0003,400
32,400116,900
0116,900

FY 2014

FY 2015

FY 2016

0
0

0
0

0
0

0
30,000030,000

0
0
0
0

0
0
0
0

FY 2017
0
0
0
0
0
0

FY 2018 Outyears
0
0
0
0
0
0
0
0
0
0
0
0

Total
1,038,000
84,0001,122,000
1,077,051
44,9491,122,000

Prior actuals adjusted to incorporate project funds utilized at PPPL and DOE. Obligation adjusted to reflect year-end PPPL
settlement funding.
bAppropriations prior to FY 2014 reflect major item of equipment funding. Starting in FY 2014, this project is funded as a
Congressional control point.
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173

FY 2008

FY 2009 a

FY 2010

FY 2011

FY 2012 b

FY 2013 c

FY 2014 d

FY 2015

FY 2016
FY 2017a

FY 2018

a

TEC
OPC
TPC
TEC
OPC
TPC
TEC
OPC
TPC
TEC
OPC
TPC
TEC
OPC
TPC
TEC
OPC
TPC
TEC
OPC
TPC
TEC
OPC
TPC
TEC
OPC
TPC
TEC
OPC
TPC
TEC
OPC
TPC

Prior
Years
931,330
43,770975,100
266,366
38,075
304,441
294,366
70,019364,385
379,366
65,019444,385
394,566
75,019469,585476,296
73,089549,385476,296
73,089549,385
481,940
67,445549,385
481,940
67,445549,385
481,940
67,445549,385
481,665
67,720549,385

FY 2013116,900
0116,900
0
0
0
0
0
0
0
0
0
0
0
0
140,965
9,035
150,000
105,57270
105,642
121,465
2,535
124,000
121,465
2,535
124,000
121,499
2,535
124,034
121,440
2,560
124,000

FY 201430,000030,000
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
225,0000
225,000
194,500
5,000
199,500
194,500
5,000
199,500
194,500
5,000
199,500
194,500
5,000
199,500

FY 2015
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
144,6395,361
150,000
144,6395,361
150,000
144,6395,361
150,000
144,6395,361
150,000

FY 2016
0
0
0
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
150,0000
150,000
115,0000
115,000
115,0000
115,000

FY 2017
0
0
0
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
125,0000
125,000
50,000050,000FY 2018 Outyears
Total0
0 1,078,230
0043,7700
0 1,122,000
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
63,000
TBD
TBD
0
TBD
TBD
63,000TBD
TBD

The Prior Years column for FY 2009 through FY 2012 reflects the total of appropriations and funding requests only throughthe year of that row. Thus, for example, in the FY 2010 row, it reflects only funding from FY 2006 to FY 2012.
b
The FY 2012 request was submitted before a full-year appropriation for FY 2011 was in place, and so FY 2011 was TBD atthat time. Hence, the Prior Years column for FY 2012 reflects appropriations for FY 2006 through FY 2010 plus the FY 2012
request.
c
The FY 2013 amount shown in the FY 2014 request reflected a short-term continuing resolution level annualized to a fullyear and based on the FY 2012 funding level for ITER.
dPrior to FY 2015, the requests were for a major item of equipment broken out by TEC, OPC, and TPC.
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174