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. Theinterdisciplinary nature of modern fusion research is emphasized in the 2015 Quadrennial Technology Review.
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.
The knowledge base being established through FES research supports U.S. goals for future scientific exploration on ITER, amajor international fusion facility currently under construction in St. Paul-lez-Durance, France. ITER will be the world’s firstmagnetic confinement long-pulse, high-power burning plasma experiment aimed at demonstrating the scientific andtechnical feasibility of fusion energy. Execution and oversight of the U.S. contribution to the ITER project are carried out
within FES.
To support the program mission and its major focus, the U.S. fusion program has four elements:

Burning Plasma Science: Foundations;
Burning Plasma Science: Long Pulse;
Burning Plasma Science: High Power; andDiscovery Plasma Science.

Highlights of the FY 2017 Budget Request
Notable changes in the FY 2017 budget include:No funding is provided for Alcator C-Mod operation and research—after the final year of operation of Alcator C-Mod in
FY 2016, the research staff at the MIT Plasma Science and Fusion Center will shift focus to begin full-time collaborative
research activities in the DIII-D and NSTX-U national research programs; in addition, some will engage in collaborations
with international laboratories.
 Increased support for DIII-D and National Spherical Torus Experiment-Upgrade (NSTX-U) research—Funding for the DIIID and NSTX-U research programs is increased to address the high priority fusion science issues identified by thecommunity research needs workshops held in FY 2015 and to support enhanced collaborations with MIT researchers.
 Continued support to the U.S. Contributions to ITER Project—Funding will support continued progress on in-kind
hardware contributions, including central solenoid superconducting magnet modules and structures, toroidal fieldmagnet conductor, steady­state electrical network components, and tokamak cooling water system. Funding is also
provided toward the FY 2017 monetary contribution to the ITER Organization, which supports ITER Project common
expenses.
 In the FY 2017 Budget Request, most funding for the Working Capital Fund (WCF) is transferred to Program Direction toestablish a consolidated source of funding for goods and services provided by the WCF. CyberOne is still fundedthrough program dollars in the SC Safeguards and Security program. In FY 2016 and prior years, WCF costs were sharedby SC research programs and Program Direction.
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FY 2017 Congressional Budget Justification
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Fusion Energy Sciences
Funding ($K)

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
SBIR/STTR:
 FY 2015 Transferred: SBIR $8,906,000 and STTR $1,228,000
 FY 2016 Projected: SBIR: $9,333,000; STTR: $1,400,000
 FY 2017 Request: SBIR $8,436,000 and STTR $1,186,000ab

FY 2015 Enacted

FY 2015 Current a

FY 2016 Enacted

FY 2017 Request b

FY 2017 vs.
FY 2016

105,348
72,91934,6703,125
216,062

107,675
71,16935,0063,600
217,450

101,255
74,00033,5006,000
214,755

84,23873,19933,1705,000
195,607-17,017-801-330-1,000-19,148

7,695
6,419
24,842
38,956

7,895
8,010
23,03338,9388,500
7,269
25,252
41,021

6,045
5,084
20,22631,355-2,455-2,185-5,026-9,66646,024
3,575
12,88362,482
317,500

44,6433,575
2,760
50,978307,366

46,7846,700
13,74067,224
323,000

31,9164,000
10,30046,216273,178-14,868-2,700-3,440-21,008-49,822150,000
467,500

150,000
457,366

115,000
438,000

125,000
398,178+10,000-39,822

Reflects the transfer of Small Business Innovation/Technology Transfer Research (SBIR/STTR) funds within the Office of Science.
A transfer of $861,000 to Science Program Direction to consolidate all Working Capital Funds in one program.

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Fusion Energy Sciences
Explanation of Major Changes ($K)
FY 2017 vsFY 2016
Burning Plasma Science: Foundations: Overall funding for advanced tokamak research is decreased, as operation of Alcator C-Mod ceases. Funding for
DIII-D and NSTX-U research is increased to support the enhanced collaboration by MIT research staff in those programs. Funding for Theory &Simulation is increased to accelerate progress toward whole-device modeling. Decreased funding for DIII-D and NSTX-U operations results indeferment of some facility enhancements and a slight reduction to operating weeks.

-19,148

Burning Plasma Science: Long Pulse: Overall funding is decreased for U.S. research collaborative activities on overseas long-pulse tokamaks andstellarators and on research and experimental capabilities that address the plasma-materials interface scientific challenge.

-9,666

Discovery Plasma Science: Overall funding is decreased, as the High Energy Density Laboratory Plasma science activity contracts to focus on supporting
research utilizing the Matter in Extreme Conditions instrument of the Linac Coherent Light Source at the SLAC National Accelerator Laboratory.
Decreases in Measurement Innovation and General Plasma Science activities result from the completion of targeted research enhancements fully
funded in FY 2016.

-21,008

Construction: Funding is provided toward the FY 2017 monetary contribution (total $44M) to the ITER Organization.

+10,000

Total Funding Change, Fusion Energy Sciences-39,822

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FY 2017 Congressional Budget Justification

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 National Science Foundation (NSF), with research extending to a wide range ofnatural phenomena, including the origin of magnetic fields in the universe and the heating of the solar corona. Also, FES
operates a joint program with the National Nuclear Security Administration (NNSA) in High Energy Density Laboratory
Plasma (HEDLP) physics. Both programs involve coordination of solicitations, peer reviews, and workshops. The Fusion
Energy Sciences Advisory Committee (FESAC) provides technical and programmatic advice to FES and NNSA for the joint
HEDLP program.
Program Accomplishments
Completion of the NSTX Upgrade project—the research capabilities of the NSTX user facility have been enhanced bydoubling its maximum toroidal field and plasma current, lengthening the pulse length, and adding a second set of neutralbeam sources for off-axis heating and current drive. These improvements make the NSTX-U experiment the highest
performing spherical tokamak in the world and will allow NSTX-U researchers to explore unique spherical tokamak
parameter regimes to advance predictive understanding of magnetically confined plasmas.
ITER component production and major deliveries—The U.S. ITER Project began the challenging task of winding the first 100ton module for the ITER central solenoid, which, when completed, will be the most powerful pulsed superconducting
electromagnet ever produced. U.S. vendors also successfully delivered one 100-meter superconducting length and two 800meter production lengths of active conductor to the European Union’s Toroidal Field Coil fabricator in Italy, and four lots ofhigh-voltage substation transformers, which are part of the steady state electric network, to the ITER site. The U.S. ITER
Project also completed fabrication and delivery of all five nuclear-grade tokamak cooling water system drain tanks.
First fully remote operation of an overseas tokamak—the first-ever fully remote operation of the Experimental Advanced
Superconducting Tokamak (EAST) tokamak in China was carried out by U.S. scientists from a purpose-built remotecollaboration room at General Atomics. The integrated China/U.S. experimental team studied axisymmetric controllability
and vertical displacement disruption events over six-hour periods on two consecutive days. Operating EAST remotely during
the nighttime in China but during the U.S. working daytime is a key milestone in the DOE Scenarios and Control
International Collaboration that involves several U.S. institutions. This approach is expected to enable EAST to achieve 24hour utilization and effectively offer use of a full campaign of experimental time to U.S. scientists during its operating
periods. Further remote operation sessions are being planned for next year.
Shining a light on the composition of the Sun—A discrepancy exists between theoretical models (based on spectroscopic
observations) that describe the relative abundances of elements in the Sun and measurements of the solar interior that are
made with acoustic wave observations. Scientists with the Z facility at Sandia National Laboratories discovered that the
wavelength-dependent radiation absorption (opacity) of iron, heated to 2.2 million degrees Kelvin, is 30–400 percent higher
than theoretically predicted. These new measurements suggest that the true opacity of solar matter is higher thanpreviously believed, altering theoretical models of the sun in a direction that brings them closer to the helio-seismologicalobservations. These results have impacted our understanding of the life cycle of the Sun and stellar evolution.
Chirping radio signals from space recreated in the laboratory—Researchers at the University of California, Los Angeles,
successfully excited elusive plasma waves, known as whistler-mode chorus waves, in the Basic Plasma Science Facility’s
Large Plasma Device. Previously these waves had only been studied in the Earth’s near-space environment. They wereaccidentally discovered during World War I by radio operators, who dubbed them “dawn chorus” since the radio signal of
the waves sounded like the chirping of birds. These waves, which occur naturally in the Earth’s magnetosphere, accelerate
electrons to extremely high energies and are responsible for the creation of the Van Allen radiation belt encircling the
Earth, which pose a threat to satellites in orbit. These new experiments allowed researchers, for the first time, to test undercontrolled laboratory conditions the current understanding of nonlinear excitation of whistler waves.
Fine-tuning tokamak magnetic fields to mitigate damaging energy bursts—Plasma confined by magnetic fields in a tokamak
device is subject to intense heat bursts, called Edge Localized Modes (ELMs), which can damage the walls of the confining
vessel. It had been known that ELMs could be suppressed by the application of small three-dimensional (3-D) magnetic
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fields at the edge of the tokamak plasma; unfortunately, doing so often destabilized the central core of the plasma. Utilizing
a newly enhanced magnetic diagnostic system on DIII-D, a multi-institutional team of scientists found that application of a
3-D perturbative magnetic field that encircles the tokamak twice will mitigate the ELMs without adversely affecting the coreplasma. The new results suggest further possibilities for tuning the magnetic fields to make ELM control easier. Thesefindings point the way to overcoming a persistent barrier to sustained fusion reactions.
Multi-scale simulations of tokamak plasma confinement—High temperature plasmas are a soup of positively charged ionsand negatively charged electrons. While faithful computer simulations of ion transport and confinement in hightemperature tokamak plasmas are now fairly standard, accurate simultaneous simulation of the electrons has proven very
difficult due to their factor-of-2000 mass difference with ions. Recently, gyrokinetic simulations of both ion and electrontransport dynamics, involving widely disparate time and space scales, have been successfully performed for the first timewith a realistic ion/electron mass ratio. The simulations used 100 million CPU hours, mostly on the Edison supercomputer at
the National Energy Research Scientific Computing Center (NERSC) user facility. The results demonstrated that such multiscale simulations are required to match with the experimentally measured ion and electron thermal fluxes and profiles andthus resolved a longstanding mystery of electron heat conduction in tokamaks.
Helium bubble formation in fusion materials—it has been known for some time that neutrons from fusion reactions cancause bubbles of helium to form within plasma-facing materials, such as tungsten, which will be used in the ITER tokamak.
These bubbles grow and can burst violently when they migrate to the surface, resulting in releases of debris that are
detrimental to the plasma. This process of bubble formation, which is important for predicting large-scale material
response to the extreme fusion environment, has been studied with atom-based simulations using resources at NERSC andthe Oak Ridge Leadership Computing Facility. The results show how the growth rate can affect the bubble size, shape,pressure, and surface damage. This information is critically important to accurately predict how a tokamak divertor
component made of tungsten behaves under fusion conditions.

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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, including developing the predictive understanding needed for ITER operations and providing solutions
to high-priority ITER concerns.
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 2017 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 ITER and future fusion reactors. Near-term targeted efforts
address scientific issues important to the ITER design. Longer-term research focuses on advanced scenarios to maximize
ITER performance. Another high-priority DIII-D research area is foundational fusion science, pursuing a basic scientificunderstanding across all fusion plasma topical areas.
The Alcator C-Mod facility at the Massachusetts Institute of Technology continued operation in FY 2016 to complete
student research and experimental work. The facility will cease operations by the end of FY 2016.
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 Princeton Plasma Physics Laboratory (PPPL) is designed to explore the physics of plasmas
confined in a spherical torus (ST) configuration. A major advantage of this configuration is the ability to confine plasma at apressure that is high compared to the magnetic field energy density, which could lead to the development of more compact
and economical future fusion research facilities based on the ST concept. The ST configuration, with its very strong
magnetic curvature, has different confinement and stability properties from those of conventional tokamaks.
The NSTX-U Major Item of Equipment (MIE) project was completed in FY 2015. The upgrade of the center stack assembly
enables a doubling of the magnetic field and plasma current and an increase in the plasma pulse length from 1 to 5
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FY 2017 Congressional Budget Justificationseconds, making NSTX-U the world’s highest-performance ST. The addition of a second neutral beam system doubles theavailable heating power and makes it possible to achieve higher plasma pressure and improve its current drive efficiency
and profile control to achieve fully non-inductive operation. Together, these upgrades support a strong research program todevelop the improved understanding of the ST configuration required to establish the physics basis for next-step ST
facilities and broaden scientific understanding of plasma confinement. The capability for controllable fully non-inductive
current drive will also contribute to an assessment of the ST as a potentially cost-effective path to fusion energy.
During its first year of research operations in FY 2016, NSTX-U will achieve magnetic fields and plasma currents about one
and a half times higher than those prior to the upgrade project. During FY 2017, NSTX-U will achieve the design values forthe magnetic field and plasma current, which are twice those achieved in NSTX.
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 Scientific Discovery through Advanced Computing (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 hugely valuable for enabling
whole-device modeling that can integrate simulations of physics phenomena across a wide range of disparate time andspace 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 needs andpriorities of ITER and burning plasmas. Three of these centers are set up as partnerships between FES and Advanced
Scientific Computing Research (ASCR).
GPE/GPP/Infrastructure
Funding in this category provides support for general infrastructure improvements at the PPPL site consistent with the PPPL
Campus Modernization Plan. This funding is based upon an analysis of safety requirements, equipment reliability, facility
improvements, 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 2017 Request

Advanced Tokamak $101,255,000
DIII-D Research ($35,000,000)
DIII-D Operations ($45,000,000)
Operations funding supports fifteen weeks of research
operations at the DIII-D facility, with experiments
focusing on high-priority advanced tokamak issues andresearch needs as identified by the FY 2015
community workshops. Areas of research include
studies of transport and radiative processes indetached divertor conditions, disruption physics andmitigation systems, and stability control strategies forrobust high performance operation. Targetedenhancements to the facility involve 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.

$84,238,000
DIII-D Research ($37,000,000)
DIII-D Operations ($44,100,000)
Operations funding supports fourteen weeks ofresearch operations at the DIII-D facility. Research will
be conducted to prepare for burning plasmas in ITER,
determine the optimal path to steady-state tokamak
plasmas, and develop the plasma material interaction
boundary solutions necessary for future devices.
Specific research goals will involve testing thepredictive models of fast ion transport by multiple
Alfven eigenmodes, studying the physical processes
that determine the edge pedestal density structure,and examining the impurity generation and transport
from the high-Z coated tiles. Targeted enhancements
to the facility will involve completion andcommissioning of an additional high-power microwave
heating system, as well as continued work on
improving the neutral beam heating control systemand designing the modifications necessary for a second
off-axis and co-/counter-directed neutral beam.

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Explanation of Change
FY 2017 vs. FY 2016-$17,017,000
DIII-D Research (+$2,000,000)
DIII-D Operations (-$900,000)
Increases in research funding will support theenhanced collaboration in the DIII-D national research
program by the MIT scientific staff, while decreases inoperations funding will delay some planned facility
enhancements and require a reduction of operating
weeks.

FY 2017 Congressional Budget Justification

FY 2016 Enacted

FY 2017 Request

Explanation of Change
FY 2017 vs. FY 2016
C-Mod Research (-$6,145,000)
C-Mod Operations (-$11,855,000)
Support for Alcator C-Mod operation and researchends in FY 2016, and the MIT research staff will begin
collaborative research activities at other national andinternational facilities.

C-Mod Research ($6,145,000)
C-Mod Operations ($11,855,000)
Operations funding supports five weeks of research
operations at the Alcator C-Mod facility in its final yearof operation in FY 2016. Research is focused on
research needs as identified by the FY 2015
community workshops. Experiments are conducted to
study disruption physics and mitigation techniques,develop the database for the critical interactions
between the plasma and material components under
ITER and reactor-relevant conditions, explore robust
high-performance stationary regimes free of Edge
Localized Modes, and advance radiofrequency heating
and current drive technology and physics
understanding. The facility will be closed after final
operations. The scientific staff will complete analysis ofexisting C-Mod data and begin making a transition tocollaborative research activities on other researchfacilities.

C-Mod Research ($0)
C-Mod Operations ($0)
Operation of Alcator C-Mod ceases. No funding isrequested for this element.

Enabling R&D ($2,165,000)
Support continues to be provided for research insuperconducting magnet technology and fueling andplasma heating technologies to enhance theperformance for existing and future magnetic
confinement fusion devices.

Enabling R&D ($2,165,000)
Support will continue 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 ($1,090,000)
Small-scale tokamak plasma research provides
experimental data in regimes of relevance to themainline advanced tokamak magnetic confinement
efforts and helps confirm theoretical models andsimulation codes in support of the goal to develop an
experimentally validated predictive capability formagnetically confined fusion plasmas.

Small-scale Experimental Research ($973,000)
Small-scale Experimental Research: (-$117,000)
Research will continue to provide experimental data in Experimental research and modeling efforts are
regimes relevant to mainline tokamak confinement and reduced.
experimental validation of models and codes.

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Enabling R&D ($0)
Research efforts are maintained at the FY 2016
Enacted level.

FY 2017 Congressional Budget Justification

Explanation of Change
FY 2017 vs. FY 2016

FY 2016 Enacted

FY 2017 Request

Spherical Tokamak $74,000,000
NSTX-U Research ($30,000,000)
NSTX-U Operations ($41,000,000)
NSTX-U begins operations after successful completionof the upgrade. Machine performance is 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 are studied. The NSTX-U team also
conducts experiments on disruption physics and on
high-priority research needs as identified by the
FY 2015 community workshops. In mid-FY 2016, a
machine vent is scheduled to install a row ofmolybdenum tiles in the lower divertor region. A totalof 18 weeks of operation is planned in FY 2016.

$73,199,000
NSTX-U Research ($31,410,000)
NSTX-U Operations ($39,090,000)
The NSTX-U team will extend performance to full fieldand current (1 Tesla, 2 mega Amps—which is double
what had been achieved prior to the upgrade).
Experiments will address divertor heat flux mitigationand plasma confinement at full parameters, assess theperformance and impact of the molybdenum divertor
tiles, and continue experiments on high-priority
research needs as identified by the FY 2015 community
workshops. Also, the team will begin experiments on
fully non-inductive current drive and sustainment.
Finally, the team will begin to develop scenarios forachieving and controlling high-performance discharges.
A total of 16 weeks of operation is planned in FY 2017.

-$801,000
NSTX-U Research (+$1,410,000)
NSTX-U Operations (-$1,910,000)
Increases in research funding will support theenhanced collaboration in the NSTX-U national
program by the MIT research staff, while decreases inoperations funding will delay some planned facility
enhancements and require a reduction of operating
weeks.

Small-scale Experimental Research ($3,000,000)
Small-scale spherical torus plasma research provides
experimental data in regimes of relevance to themainline spherical torus magnetic confinement efforts
and helps 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 ($2,699,000)
Research will continue to provide experimental data inregimes relevant to mainline spherical torus
confinement and experimental validation of models
and codes.

Small-scale Experimental Research (-$301,000)
Experimental research and modeling efforts are
reduced.

Theory & Simulation $33,500,000
Theory ($24,000,000)
The Theory activity continues to advance the scientificunderstanding of the fundamental physical processes
governing the behavior of magnetically confinedplasmas. Emphasis on addressing ITER priorities
continues to guide the selection of new and renewal
awards via competitive merit reviews.

$33,170,000
Theory ($21,170,000)
Theoretical research at universities, private industry
and national laboratories will continue to address
fundamental questions of magnetic confinement
science. The selection of new awards via competitive
merit reviews will place emphasis on closing gaps inburning plasma science as identified by the community
workshops held in FY 2015 and on addressing highpriority needs of integrated simulation efforts.

-$330,000
Theory (-$2,830,000)
The reduction will result in approximately six fewer
awards being made to universities and private
industry, relative to FY 2016, under the annual Theory
Funding Opportunity Announcement. Efforts at thenational laboratories will be held flat with the FY 2016
Enacted level.

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FY 2017 Congressional Budget Justification

Explanation of Change
FY 2017 vs. FY 2016
SciDAC ($9,500,000)
SciDAC ($12,000,000)
SciDAC (+$2,500,000)
The five SciDAC centers, pending a positive outcome of The new SciDAC centers, selected via a competitive
The increased funding will strengthen integration
the merit review held in FY 2015, enter the final year
merit review and set up as partnerships with ASCR, will efforts and accelerate progress toward whole-deviceof their research activities, while the three FES–ASCR
start their research activities. The new portfolio willmodeling.
SciDAC-3 partnerships continue their efforts in thehave a strong emphasis on integration and wholeareas of boundary physics, materials science, anddevice modeling, focusing on the highest-priority
multiscale integrated modeling. FES and ASCR develop research directions as identified by the community
a plan emphasizing integration for the science areas
workshops held in FY 2015. This area supports Clean
represented by the entire FES SciDAC portfolio andEnergy.
initiate preparations for a competitive merit review.
FY 2016 Enacted

GPE/GPP/Infrastructure $6,000,000
Continued support of NSTX-U operations, as well as
enhanced International Collaborations, is provided
through improvements to the Princeton Plasma
Physics Laboratory Computer Center (PPPLCC) andestablishment of remote collaboration room
configurations. Environmental monitoring needs at
PPPL will continue to be supported.

Science/Fusion Energy Sciences

FY 2017 Request$5,000,000
Funding will provide support for general infrastructure
improvements for the PPPL site consistent with the
PPPL Campus Modernization Plan, based upon an
analysis of safety requirements, equipment reliability,
and research-related infrastructure needs.

148-$1,000,000
Funding maintains infrastructure repairs andmaintenance, as well as, modernization of laboratory
infrastructure, consistent with the PPPL Campus
Modernization Plan, although the reduction slows thepace of the campus modernization efforts.

FY 2017 Congressional Budget Justification

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 required towithstand the extreme conditions in a burning plasma environment. The key objectives of this area are to utilize these newcapabilities to accelerate 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 andstellarator research and fusion nuclear science and materials research.
Long Pulse: Tokamak
Multi-institutional U.S. research teams will be supported to continue their successful work on the long-pulse international
tokamaks that came on-line in the last few years. These collaborative teams are building on the experience gained from U.S.
fusion facilities to conduct high-impact long-pulse research on the international tokamaks either onsite or via remote
operation. Long plasma pulse research will enable the exploration of new plasma physics regimes and allow the U.S. fusion
program to gain the knowledge needed to operate long plasma discharges in ITER and other fusion energy devices.
Long Pulse: Stellarator
Stellarators offer steady-state confinement regimes eliminating transient events such as harmful disruptions. The 3-D
shaping of the plasma in a stellarator provides for a broader range in design flexibility than is achievable in a 2-D system.
The participation of U.S. researchers on Wendelstein 7-X (W7-X) in Germany provides an opportunity to develop and assess
3D divertor configurations for long-pulse, high-performance stellarators. The U.S. plans to develop control schemes tomaintain plasmas with stable operational boundaries, including the challenges of control with superconducting coils andissues 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, with opportunities for full U.S. participation 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
and Fusion Nuclear Science element supports the development, characterization, and modeling of structural, plasma-facing,and blanket materials used in the fusion environment. Materials that can withstand this environment, under the long-pulse
or steady-state conditions anticipated in future 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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Fusion Energy Sciences
Burning Plasma Science: Long Pulse
Activities and Explanation of Changes

Explanation of Change
FY 2017 vs. FY 2016

FY 2016 Enacted

FY 2017 Request

Long Pulse: Tokamak $8,500,000
U.S. scientists will develop, install, and commission
improved plasma control feedback systems for China’s
Experimental Advanced Superconducting Tokamak(EAST) and Korea’s Superconducting Tokamak
Advanced Research (KSTAR). ITER operating scenarios
will be explored and evaluated on EAST and KSTAR.
Radio-frequency heating and current drive and neutralbeam injection actuator models for EAST and KSTAR
will be developed and validated.

$6,045,000
Multi-institutional U.S. research teams will continue
to conduct high-impact research on the international
superconducting long-pulse tokamaks, taking
advantage of their upgraded capabilities.

-$2,455,000
The program will reduce the overall level of effort andwill defer some scheduled research tasks. There will be
additional limitations to the on-site presence of U.S.
researchers, which will shift emphasis to remote
operations.

Long Pulse: Stellarators $7,269,000
Superconducting Stellarator Research ($4,200,000)
U.S. scientists are participating in the first plasma
operating campaign of W7-X. The U.S. team will be
involved with characterizing the 3-D magnetic
configuration and performing the first tests of U.S.supplied equipment during plasma operation. The
team will also prepare the Test Divertor Unit (TDU)
scraper element for the second operating campaign.

$5,084,000
Superconducting Stellarator Research ($2,515,000)
U.S. scientists will participate in W7-X research on
topics important for understanding the physics oflong-pulse plasma confinement in 3-D magnetic
configurations. Topics include error fields, magnetic
island physics, energetic-particle transport, impurity
studies, plasma-material interactions, core plasmatransport, and plasma control. The U.S. team will
collaborate in the preparation of equipment andplasma scenarios for long-pulse operation.

-$2,185,000
Superconducting Stellarator Research (-$1,685,000)
The program will reduce participation by U.S.
researchers in the second plasma operating campaign ofthe W7-X experimental activities.

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Explanation of Change
FY 2017 vs. FY 2016
Compact Stellarator Research (-$500,000)
Experimental research and modeling efforts will be
reduced.

FY 2016 Enacted

FY 2017 Request

Compact Stellarator Research ($3,069,000)
Compact stellarator research provides experimental
data in regimes of relevance to the mainline stellarator
magnetic confinement efforts and helps confirm
theoretical models and simulation codes in support of
the goal to develop an experimentally validated
predictive capability for magnetically confined fusion
plasmas.

Compact Stellarator Research ($2,569,000)
Research will continue on experiments that areproviding data in regimes relevant to mainline
stellarator confinement and experimental validationof models and codes

Materials & Fusion Nuclear Science $25,252,000
Fusion Nuclear Science ($11,252,000)
The focus remains the utilization of existing
experimental capabilities to conduct research in theareas of plasma-facing materials and plasma-materialinteractions consistent with the high-priority researchneeds identified by the FY 2015 community
workshops. Research toward understanding tritium
retention and permeation, neutronics, and materialcorrosion issues for blankets continues. Scoping
studies continue on characterizing significant researchgaps in the materials and fusion nuclear sciences
program.

$20,226,000
Fusion Nuclear Science ($10,000,000)
Utilization of existing experimental capabilities anddevelopment of new ones to conduct research in theareas of plasma-facing materials and plasmamaterial interactions will be a key emphasis. In
addition, research on understanding tritium
retention, permeation and processing, neutronics,
and material-corrosion issues for blankets andscoping studies on future fusion facilities willcontinue.

Materials Research ($14,000,000)
The focus remains the utilization of existing
experimental capabilities to conduct research in thearea of material response to simulated fusion neutron
irradiation consistent with the high-priority researchneeds identified by the FY 2015 community
workshops. Research toward structural materials thatcan withstand high levels of damage, increasing theductility of tungsten, and modeling of helium damage
in numerous materials continues.

Materials Research ($10,226,000)
Materials Research (-$3,774,000)
The program will emphasize the utilization of existing The program will decrease research efforts across thisexperimental capabilities and development of new
program element.
ones to conduct research in the area of material
response to simulated fusion neutron irradiation.
There will be a continued focus on research toward
structural materials that can withstand high levels ofdamage, increasing the ductility of tungsten, andmodeling of helium damage in numerous materials.

Science/Fusion Energy Sciences151-$5,026,000
Fusion Nuclear Science (-$1,252,000)
The program will reduce research efforts across thisprogram element.

FY 2017 Congressional Budget Justification

152

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, ranging from energy efficient lighting toatmospheric pressure plasma for medical applications.
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 ultracold (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 translate 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
neutral 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 – Structural and dynamical studies of ionized matter at extreme densities andtemperatures.
Exploratory Magnetized Plasma – Basic and applied research directed at developing the understanding of magnetizedplasma behavior necessary to advance innovative solutions and capabilities for the creation, control, and manipulationof magnetically confined plasmas for terrestrial and space applications.

This subprogram maintains a leadership role in the national stewardship of plasma science by partnering with the National
Science Foundation (NSF) and the National Nuclear Security Administration (NNSA) and by leveraging access to best-in-classexperimental facilities as well as stewarding and operating world-class plasma science user facilities at small andintermediate scales. Along with facilitating discovery, intermediate-scale platforms are also providing critical data for theverification and validation of plasma science codes.
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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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 the Fusion Energy
Sciences Advisory Committee (FESAC).

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Fusion Energy Sciences
Discovery Plasma Science
Activities and Explanation of Changes
FY 2016 Enacted

FY 2017 Request

Plasma Science Frontiers $46,784,000
General Plasma Science ($16,125,000)
Research continues 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 is enhanced.

$31,916,000
General Plasma Science ($15,500,000)
Core research elements of this activity will continue.

Explanation of Change
FY 2017 vs. FY 2016-$14,868,000
General Plasma Science (-$625,000)
The program will reduce support for user research on
major FES user facilities.

High Energy Density Laboratory Plasmas ($20,250,000) High Energy Density Laboratory Plasmas ($7,000,000)
Research emphasizes utilizing the Matter in Extreme
Conditions (MEC) instrument at the Linac Coherent
Light Source 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 is supported through new research grants aspart of the SC/NNSA Joint Program in HEDLP and the
NSF/DOE Partnership in Basic Plasma Science andEngineering, as well as operation of the Neutralized
Drift Compression Experiment-II (NDCX-II).
Exploratory Magnetized Plasma ($10,409,000)
This portfolio will be evaluated through a competitive
peer-review process.

Science/Fusion Energy Sciences

High Energy Density Laboratory Plasmas(-$13,250,000)
Research will emphasize utilizing the MEC at LCLS,
Contraction of the HEDLP program will result in no
including continued support for the MEC beam-line
new research activities at either universities or DOE
science team, the HEDLP research group at SLAC, and national laboratories and the cessation of operations
enhanced support of external HED science users of the and research at the NDCX-II.
MEC instrument.

Exploratory Magnetized Plasma ($9,416,000)
Research direction and emphasis will be informed by
the high-priority research as identified by the plasma
science frontiers workshops held in FY 2015.

155

Exploratory Magnetized Plasma (-$993,000)
The program will reduce research efforts and/or scope,taking into consideration the outcomes of the plasma
science frontiers workshops held in FY 2015.

FY 2017 Congressional Budget Justification

FY 2016 Enacted

FY 2017 Request

Explanation of Change
FY 2017 vs. FY 2016

Measurement Innovation $6,700,000
Core research elements of the Measurement
Innovation activity continue with enhanced effort ondiagnostic development important to addressing thescientific issues identified in the community
workshops held in FY 2015.

$4,000,000
Measurement Innovation research activities willcontinue, with special emphasis on diagnostics forplasma transient instabilities, plasma-materials
interactions, modeling validation, and basic plasma
science.

-$2,700,000
The program will reduce funding to address scientificissues identified in the FY 2015 community workshops.

SBIR/STTR & Other $13,740,000
Funding continues to support USBPO activities, HBCUs,
peer reviews for solicitations, and FESAC. SBIR/STTR
funding is statutorily set at 3.45 percent of noncapitalfunding in FY 2016.

$10,300,000
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 2017.

-$3,440,000
The decrease is due to consolidation of funding for theWorking Capital Fund under Program Direction andreduction in the required SBIR/STTR funding.

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Fusion Energy Sciences
Construction
Description
The exploration of high-power burning (self-heated) plasmas is the next critical area of scientific research for fusion.
Previously the U.S. and European fusion programs had investigated burning plasmas at low power (10 megawatt level). The
ITER facility, currently under construction in St. Paul-lez-Durance, France, will provide access to burning plasmas with fusion
power output approaching reactor levels of hundreds of megawatts, for hundreds of seconds. ITER will thus be the firstever facility capable of assessing the scientific and technical feasibility of fusion energy. As a collaborator in the ITER
project, which was established though an international agreement (the “ITER Joint Implementing Agreement”), the U.S.
contributes in-kind-hardware components, personnel, and direct monetary funding to the ITER Organization (IO) for the
ITER construction phase, as established by the terms of the ITER Joint Implementing Agreement. The key objective of these
efforts is the completion of all activities associated with the U.S. Contributions to ITER (USITER) project.
U.S. Contributions to ITER Project
The ITER international fusion project is designed to be the first magnetic confinement fusion facility to achieve a selfsustained burning plasma. As ITER construction activities continue, careful and efficient management of the U.S.
contributions to the international project by the U.S. ITER Project Office (USIPO) at Oak Ridge National Laboratory (ORNL)
continue to be a high priority for FES.
ITER is designed to generate the world’s first sustained (300-second discharge, self-heated) burning plasma. It aims togenerate fusion power 30 times the levels produced to date and to exceed the external power applied to the plasma by atleast a factor of ten. ITER will be a powerful tool for discovery, capable of addressing the new challenges of the burning
plasma frontier and assessing the scientific and technical feasibility of fusion energy.
The ITER Project is being designed and built by an international consortium consisting of the U.S., China, India, Japan, South
Korea, the Russian Federation, and the European Union (the host); the central project execution authority is the ITER
Organization (IO). The U.S. is committed to the scientific mission of ITER and will work with ITER partners to accomplish thisgoal, while maintaining a balanced domestic research portfolio. Executing a program with well-aligned domestic andinternational components will sustain U.S. international leadership in fusion energy sciences. The U.S. magnetic fusion
research program in experiment, theory, and computation is configured to make strong contributions to ITER’s science andto bring a high level of scientific return from it. ITER joins the broader FES research portfolio in elevating plasma sciences forboth practical benefit and increased understanding.
The USITER project consists primarily of in-kind hardware components, with additional contributions of personnel and cash
to the IO for the ITER construction phase, which are established by the terms of the ITER Joint Implementing Agreement. In
exchange for the U.S. share of the ITER project, the U.S. gains access to 100 percent of the ITER research output, and U.S.
scientists may conduct their own research experiments. The U.S. contributions are managed by the USIPO at ORNL, in
partnership with PPPL and Savannah River National Laboratory (SRNL). The U.S. ITER Project is unique among major DOE
projects in that U.S. in-kind hardware contributions are delivered to the IO, which is outside direct DOE oversight andmanagement control. The risks associated with performing the installation, assembly, and commissioning work depend on
the execution of project responsibilities by the IO.
The 2013 Management Assessment of ITER found a significant number of challenges and deficiencies in the organization.
The installation of a new Director-General in April 2015 and his efforts to improve the organization’s culture and lead thedevelopment of a revised project resource-loaded long-term schedule demonstrate a positive shift in the IO. An
independent review of the updated schedule is underway, with expected delivery of the report in mid-April 2016. This will
present an opportunity to review and gauge the international commitment to the ITER project in light of significant delays
and increased costs.
The 2016 Omnibus Appropriations directed, “Not later than May 2, 2016, the Secretary of Energy shall submit to theCommittees on Appropriations of both Houses of Congress a report recommending either that the United States remain apartner in the ITER project after October 2017 or terminate participation, which shall include, as applicable, an estimate ofeither the full cost, by fiscal year, of all future Federal funding requirements for construction, operation, and maintenance of
Science/Fusion Energy Sciences
FY 2017 Congressional Budget Justification
157

ITER or the cost of termination.” There are numerous activities (e.g., 2013 Management Assessment Corrective Action Plan
performance; 2015 Management Assessment conclusions and recommendations; independent schedule review conclusions
and recommendations; ITER Council-approved milestone performance) that will factor into the decision by the Secretary ofEnergy. The $125 million requested in FY 2017 will allow the most critical USITER activities to make progress, as well as
provide cash funds for ITER Organization operations and the Director General’s Reserve Fund.The requested level offunding for FY 2017 supports U.S. in-kind hardware contributions; funds the USIPO staff and support contractors at ORNL,PPPL, and SRNL; and provides funding toward the FY 2017 monetary contribution to the IO.

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Fusion Energy Sciences
Construction
Activities and Explanation of Changes
FY 2016 Enacted

FY 2017 Request

U.S. Contributions to ITER Project $115,000,000
Funding supports continued progress on in-kind
hardware contributions, including: central solenoid
superconducting magnet modules and structures,
toroidal field magnet conductor, steady-state electrical
network components, and tokamak cooling water
system components.

$125,000,000
Funding will support continued progress on critical inkind hardware contributions, including central
solenoid superconducting magnet modules andstructures, toroidal field magnet conductor,
steady-state electrical network components,
diagnostics development, tokamak cooling water
system, and vacuum system. Funding is also provided
toward the FY 2017 cash contribution for ITER
Organization operations and Director General’sReserve Fund.

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159

Explanation of Change
FY 2017 vs. FY 2016+$10,000,000
The increase provides funding toward the cash
contribution for ITER Organization operations and the
Director General’s Reserve Fund.

FY 2017 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.
The following table shows the targets for FY 2015 through FY 2017. Details on the Annual Performance Report can be found at http://energy.gov/cfo/reports/annualperformance-reports.
Performance
Goal (Measure)
TargetResultFY 2015
FY 2016
FY 2017
FES Facility Based Experiments—Experiments conducted on major fusion facilities (DIII-D, Alcator C-Mod, NSTX-U) leading toward predictive
capability for burning plasmas and configuration optimization
Conduct experiments and analysis to quantify the Conduct research to detect and minimize theConduct research to examine the effect ofimpact of broadened current and pressure
consequences of disruptions in present andconfiguration on operating space for dissipative
profiles on tokamak plasma confinement andfuture tokamaks, including ITER. Coordinateddivertors. Handling plasma power and particle
stability. Broadened pressure profiles generally
research will deploy a disruption
exhaust in the divertor region is a critical issue
improve global stability but can also affectprediction/warning algorithm on existingfor future burning plasma devices, includingtransport and confinement, while broadened
tokamaks, assess approaches to avoid
ITER. The very narrow edge power exhaustcurrent profiles can have both beneficial anddisruptions, and quantify plasma and radiation channel projected for tokamak devices thatadverse impacts on confinement and stability.
asymmetries resulting from disruption
operate at high poloidal magnetic field is ofThis research will examine a variety of heating
mitigation measures, including both preparticular concern. Increased and controlled
and current drive techniques in order to validate existing and resulting MHD activity, as well as
divertor radiation, coupled with optimization oftheoretical models of both the actuator
the localized nature of the disruption mitigation the divertor configuration, are envisioned as
performance and the transport and global
system. The research will employ new
the leading approaches to reducing peak heatstability response to varied heating and current
disruption mitigation systems, control
flux on the divertor targets and increasing thedrive deposition.
algorithms, and hardware to help avoid
operating window for dissipative divertors. Data
disruptions, along with measurements to detect obtained from DIII-D and NSTX-U and archived
disruption precursors and quantify the effects
from Alcator C-Mod will be used to assess theof disruptions.
impact of edge magnetic configurations anddivertor geometries on dissipative regimes, aswell as their effect on the width of the power
exhaust channel, thus providing essential data
to test and validate leading boundary plasma
models.
Met
TBD
TBD

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Endpoint Target

Performance
Goal (Measure)
TargetResultEndpoint Target

Performance
Goal (Measure)
TargetFY 2015
FY 2016
FY 2017
Magnetic fields are the principal means of confining the hot ionized gas of a plasma long enough to make practical fusion energy. The detailed shapeof these magnetic containers leads to many variations in how the plasma pressure is sustained within the magnetic bottle and the degree of control
that experimenters can exercise over the plasma stability. These factors, in turn, influence the functional and economic credibility of 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 inthese magnetic configurations. The major fusion facilities can produce plasmas that provide a wide range of magnetic fields, plasma currents, andplasma shapes. By using a variety of plasma control tools, appropriate materials, and diagnostics needed to measure critical physics parameters,scientists will be able to develop optimum scenarios for achieving high performance plasmas in ITER and, ultimately, in reactors.
FES Facility Operations—Average achieved operation time of FES user facilities as a percentage of total scheduled annual operation time
≥ 90%
≥ 90%
≥ 90%
Not MetTBD
TBD
Many of the research projects that are undertaken at the SC scientific user facilities take a great deal of time, money, and effort to prepare andregularly have a very short window of opportunity to run. If the facility is not operating as expected, the experiment could be ruined or critically set
back. 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 the plasma
science of magnetic confinement
Perform massively parallel plasma turbulence
Predicting the magnitude and scaling of theLower hybrid current drive (LHCD) will besimulations to determine expected transport indivertor heat load width in magneticallyindispensable for driving off-axis current during
ITER. Starting from best current estimates of ITER confined burning plasmas is a high priority forlong-pulse operation of future burning plasma
profiles, the turbulent transport of heat andthe fusion program and ITER. One of the key
experiments including ITER, since it offers
particles driven by various micro-instabilities
unresolved physics issues is what sets the heat important leverage for controlling damaging(including electromagnetic dynamics) will be
flux width at the entrance to the divertor
transients caused by magnetohydrodynamic
computed. Stabilization of turbulence byregion. Perform massively parallel simulations
instabilities. However, the experimentally
nonlinear self-generated flows is expected tousing 3D edge kinetic and fluid codes todemonstrated high efficiency of LHCD is
improve ITER performance, and will be assessed
determine the parameter dependence of theincompletely understood. In FY 2017, massively
with comprehensive electromagnetic gyrokinetic heat load width at the divertor entrance andparallel, high-resolution simulations with 480
simulations.
compute the divertor plate heat flux applicable radial elements and 4095 poloidal modes will
to moderate particle recycling conditions.
be performed using full-wave radiofrequency
Comparisons will be made with data from DIII- field solvers and particle Fokker-Planck codes to
D, NSTX-U, and C-Mod.
elucidate the roles of toroidicity and full-wave
effects. The simulation predictions will becompared with experimental data from thesuperconducting EAST tokamak.

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Result
Endpoint Target

FY 2015
FY 2016
FY 2017Met
TBD
TBD
Advanced simulations based on high-physics-fidelity models offer the promise of advancing scientific discovery in the plasma science of magnetic
fusion by exploiting the SC high-performance computing resources and associated advances in computational science. These simulations are able toaddress the multi-physics and multi-scale challenges of the burning plasma state and contribute to the FES goal of advancing the fundamental scienceof magnetically confined plasmas to develop the predictive capability needed for a sustainable fusion energy source.

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Fusion Energy Sciences
Capital Summary ($K)
Total

Prior Years

FY 2015
EnactedFY 2015
Current

FY 2016
EnactedFY 2017
RequestFY 2017 vsFY 2016

Capital Operating Expenses Summary
Capital equipment
General plant projects (GPP)
Accelerator Improvement Projects (AIP) (<$5M)
Total, Capital Operating Expenses

n/a
n/a

n/a
n/a

7,798
2,500

11,388
2,500

6,899
5,000

5,229
4,321

-1,670
-679

n/a

n/a

10,29813,888

11,8999,550-2,349

Capital Equipment
Major items of equipment a
National Spherical Torus Experiment Upgrade(TPC $94,300)
U.S. Contributions to ITER (TPC TBD)
Total MIEs
Total Non-MIE Capital Equipment
Total, Capital equipment

83,665
TBD
n/a
n/a
n/a

80,195673,385
729,880
n/a
n/a

3,470
0
3,470
4,328
7,798

3,470
0
3,470
7,918
11,388

0
0
6,899
6,899

0
0
0
5,229
5,229

0
0
0
-1,670-1,670

n/a

n/a

2,500

2,500

5,000

4,321

-679

General Plant Projects b
General Plant Projects under $2 million TECab

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

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Fusion Energy Sciences
Construction Projects Summary ($K)
Total
14-SC-60, U.S. Contributions to ITER Project
Total Estimated Cost (TEC)
Other Project Cost (OPC)
Total, Project Cost (TPC), 14-SC-60

Prior Years

FY 2015
EnactedFY 2015
Current

FY 2016
EnactedFY 2017
RequestFY 2017 vsFY 2016

797,905
74,980872,885

144,6395,361
150,000

144,6395,361
150,000

115,0000
115,000

125,0000
125,000+10,0000+10,000

TBD
TBD
TBD

Fusion 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 2015 Enacted
216,258
94,6473,470
3,125
150,000
467,500

FY 2015 Current
205,610
94,6863,470
3,600
150,000
457,366

FY 2016 Enacted
219,145
97,8550
6,000
115,000
438,000

FY 2017 Request
184,988
83,1900
5,000
125,000
398,178

FY 2017 vs. FY 2016
-34,157-14,6650-1,000+10,000-39,822

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.

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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.
FY 2015 Enacted

FY 2015 Current

FY 2016 Enacted

FY 2017 Request a

FY 2017 vs. FY 2016

TYPE A FACILITIESDIII-D National Fusion Facility
Number of Users
Achieved operating hours
Planned operating hours
Optimal hours
Percent optimal hours
Unscheduled downtime hours$79,950
579
600
600
1,000
60%
50

$83,108
579
550
600
1,000
55%
50

$80,000
579
N/A
600
1,000
60%
N/A

$81,100
570
N/A
560
560
100%
N/A

+1,100
-9
N/A
-40
-440
+40%
N/A

Alcator C-Mod
Number of Users
Achieved operating hours
Planned operating hours
Optimal hours
Percent optimal hours
Unscheduled downtime hours$22,260
170
0
384
800
48%
0

$21,429
170
400
384
800
50%
0

$18,000
140
N/A
160
800
20%
N/A

0
0
N/A
0
0
0
N/A

-18,000
-140
N/A
-160
-800
-20%
N/A

a

For FY 2017 the number of optimal hours for DIII-D and NSTX-U is less than the typical amount due to planned enhancement activities at the facility that will preclude
operation during part of the fiscal year.
Science/Fusion Energy Sciences165

FY 2017 Congressional Budget Justification

National Spherical Torus ExperimentUpgrade
Number of Users
Achieved operating hours
Planned operating hours
Optimal hours
Percent optimal hours
Unscheduled downtime hours
Total Facilities
Number of Users
Achieved operating hours
Planned operating hours
Optimal hours
Percent of optimal hours a
Unscheduled downtime hours

FY 2015 Enacted

FY 2015 Current

FY 2016 Enacted

FY 2017 Request a

FY 2017 vs. FY 2016

$72,919$68,470$71,000$70,500

-500

250
N/A
480
500
96%
0
$168,960
999
N/A
1,464
2,300
73.1%
N/A

250
N/A
480
500
96%
480
$173,007
999
N/A
1,464
2,300
70.6%
530

329
N/A
720
1,000
72%
N/A
$169,000
1,048
N/A
1,480
2,800
60.8%
N/A

322
N/A
640
640
100%
N/A
151,600
892
N/A
1,200
1,200
100%
N/A

-7
N/A
0
-280
+28%
N/A
-17,400
-156
N/A
-280
-1,600+39.2%N/A

FY 2017 Request
625
80
200
947

FY 2017 vs. FY 2016
-142
-18
-93
-78

Scientific Employment

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

FY 2015 Enacted
724
93
268
1,102

FY 2015 Current
724
93
268
1,102

a

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

Includes technicians, engineers, computer professionals, and other support staff.

Science/Fusion Energy Sciences

166

FY 2016 Enacted
767
98
293
1,025

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

FY 2017 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 2016 CPDS and does not include a new start for FY 2017.
Summary
The FY 2017 Request for ITER is $125,000,000, $10,000,000 more than the FY 2016 Enacted level of $115,000,000. The mostrecent DOE Order 413.3B approved Critical Decision (CD) is CD-1, Approve Alternative Selection and Cost Range, which wasapproved on January 25, 2008 with a preliminary cost range of $1.45–$2.2 billion. Since CD-1, it has not been possible tobaseline the project because of continued delays in the international ITERproject construction schedule. Until CD-2 can beapproved, U.S. funding will be managed to address annual project priorities and to allow flexibility to adapt to the changing
state of the project. Since the project does not have CD-2 approval, the schedule and cost estimates contained in this CPDS
are identified as “TBD”. A substantial increase in the overall Total Project Cost of the project is anticipated once it is ready to
be baselined.
The approving official for all critical decisions is the Director of the Office of Science (SC-1).
A Federal Project Director with certification level 3 has been assigned to this project and has approved this CPDS.
ITER is a major fusion research facility being constructed in Cadarache, France by an international partnership of seven
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
(USITER) project is not classified as a capital asset project. The USITER is a U.S. Department of Energy project to provide theU.S. share of in-kind hardware (e.g., subsystems, equipment, and components), as well as cash contributions to support the
ITER organization in France. Sections of this CPDS have been tailored accordingly to reflect the nature of this project.
The USITER 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 beginning in FY 2014. This did not change SC’s overall
program and project management approach for the USITER Project. As with all SC projects, the principles of DOE Order413.3B 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 line-item projects. An approved
Annual Performance Plan (APP) authorizes the work activities to be performed, as well as establishes milestones for project
performance against which progress will be measured. Progress and performance against the APP is reported regularly inmonthly performance metrics and project status reports.
The USITER project is making significant progress in the areas of design completion and fabrication of hardware. As of theend of December 2015, the USITER project is 29% complete overall;design of all twelve technical systems the U.S. is
responsible for delivering is 58% complete; and hardare fabrication is 9% complete. Two of the largest U.S. systems, theTokamak Cooling Water System (TCWS) and the Central Solenoid (CS) Magnets, are in or beyond the final design stage.
Active fabrication is underway in four of the U.S. twelve hardware systems (TCWS, Steady State Electric Network [SSEN]
Components, Toroidal Field [TF] Conductor and CS Magnets). The U.S. has completed the fabrication and delivery of fivenuclear-grade cooling water drain tanks to the ITER site. These components, which are time critical for ITER construction
sequencing and which are fabricated in accordance with French Nuclear regulations, are some of the first major hardware
components delivered to the site in France. The U.S. has also been procuring 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 are continuing. Fabrication of the TF conductor is also well underway. The purchaseof superconducting strand material is complete, and cabling activities are well underway with four of the nine lengths
completed through November 2015. Jacketing of three conductor lengths has been completed. The U.S. has shippedfinished lengths of conductors to the European Union, one of the ITER Members responsible for TF Magnet fabrication, andfabrication of TF conductor and final delivery will be completed in early FY 2017. The U.S. has contracted with General
Atomics (GA) for the fabrication of the world’s largest superconducting magnets for the ITER CS Magnet system. The GA
fabrication facility is essentially complete and commissioning is complete for six of the eleven work stations needed for
Science/Fusion Energy Sciences/
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FY 2017 Congressional Budget Justification

fabrication of each of the seven modules the U.S. is responsible for delivering. In FY 2015, the U.S. started fabrication of amockup (non-superconducting) coil to provide assurance of manufacturing processes; and most notably, started thewinding of the first production module with superconducting CS conductor provided by the Japanese Domestic Agency.
Initiation of fabrication activities in the GA facility represents the culmination of several years of preparation and a major
accomplishment for the USITER project. By the end of CY 2017, all modules will be in fabrication. DOE has begun to award
contracts for the assembly tooling necessary for CS Magnet installation in the ITER facility with fabrication of all toolingplanned for FY 2018 completion, and contracts for CS Structures has begun with deliveries beginning in FY 2017 and planned
fabrication complete in FY 2019. To date the USITER project has awarded and obligated over $794 million to U.S. industry,
universtities, and DOE laboratories.
FY 2016 funding supports continued in-kind contributions and related support activities. No funding is provided for cash
contributions to support the ITER organization in FY 2016. FY 2017 funding will support ITER Project Office operations, theU.S. cash contribution to the ITER Organization, and continued progress on U.S. in-kind contributions, including: central
solenoid magnet modules and structures, toroidal field magnet conductor, steady state electric network, diagnostics
development, tokamak cooling water system, and vacuum system.
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

a

Electron 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).
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).
df

Steady State Electrical Network (05/02/2012).
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).
gh

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 Assembly Tooling, Early Items (09/17/14).
CS Modules and Structures (11/18/2013); VAS Main Piping B-2, L-1, L-2 (12/10/2013).
k
CS AT Remaining Items; VAS 02 Supply; VAS Main piping (L3-L4); Pellet Injection Flight Tubes.
l
TCWS Captive Piping; ICH Gallery: Radio Frequency (RF) Building; Port Plug Test Facility Transmission Line (PPTF TL); ECH TL
System Design; RGA; Upper VIR Cameras; LFS.
Science/Fusion Energy Sciences/
FY 2017 Congressional Budget Justification
168
14-SC-60, U.S. Contributions to ITERj

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 Completion
3.

Project Cost History

At the time of CD-1 approval in January 2008, the preliminary cost range was $1.45–$2.2 billion. Since then, however, it has
not been possible to confidently baseline the project due to continued delays in the international 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.
DOE anticipates a substantial increase in the overall Total Project Cost of the project once the project is ready to bebaselined.
4.

Project Scope and Justification

Introduction
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 USITER
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.
Scope
ITER Construction Project Scope
The USITER project includes three major elements:Hardware components, built under the responsibility of the U.S., then shipped to the ITER site for IO assembly,
installation, and operation.
Funding to the IO to support common expenses, including ITER research and development (R&D), IO staff andinfrastructure, IO-provided hardware, on-site assembly/installation/testing of all ITER components, and IO Central
Reserve, which serves as a contingency fund.
Other project costs, including R&D and conceptual design related activities.

The USITER project hardware scope is limited to design, fabrication, and delivery of mission-critical tokamak subsystems andis described below. As of December 2015, the USITER project is 28% complete.






Tokamak Cooling Water System (TCWS): manages the thermal energy generated during the operation of the tokamak.
The TCWS is 24% complete.
15% of ITER Diagnostics: provides the measurements necessary to control, evaluate, and optimize plasma performanceand to further the understanding of plasma physics. Diagnostics are 21% complete.
Disruption Mitigation Systems ($20M cost cap): limit the impact of plasma disruptions to the tokamak vacuum vessel,blankets, and other components. The Disruption Mitigation Systems are 25% complete.
Electron Cyclotron Heating (ECH) Transmission Lines: bring additional power to the plasma and deposits power in
specific areas of the plasma to minimize instabilities and optimize performance. The ECH is 19% complete.
Tokamak Exhaust Processing (TEP) System: separates hydrogen isotopes from tokamak exhaust. The TEP system is 11%
complete.

Science/Fusion Energy Sciences/
14-SC-60, U.S. Contributions to ITER169

FY 2017 Congressional Budget Justification









Fueling System (Pellet Injection): injects fusion fuels in the form of deuterium-tritium ice pellets into the vacuum
chamber. The Pellet Injection system is 18% complete.
Ion Cyclotron Heating (ICH) Transmission Lines: bring additional power to the plasma. The ICH is 17% complete.
Central Solenoid (CS) Magnet System: confines, shapes and controls the plasma inside the vacuum vessel. The CS
Magnet modules are 56% complete; the CS structures are 26% complete; and the CS tooling is 47% complete.
8% of Toroidal Field (TF) Conductor: component of the TF magnet that confines, shapes, and controls the plasma. The
TF Conductor is 95% complete.
75% of the Steady State Electrical Network (SSEN): supplies the electricity needed to operate the entire plant,
including offices and the operational facilities. The SSEN is 59% complete.
Vacuum Auxiliary System: creates and maintains low gas densities in the vacuum vessel and connected vacuum
components. The Vacuum Auxiliary System is 20% complete,
Roughing Pumps: evacuate the tokamak, cryostat, and auxiliary vacuum chambers prior to and during operations.
Roughing Pumps system is 15% complete.

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.
The project is being conducted in accordance with the project management principles of DOE O 413.3B, Program andProject Management for the Acquisition of Capital Assets.
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 2013a
FY 2014ac
FY 2015
FY 2016 d
FY 2017
Subtotal
Total, Hardwarea13,754
34,58825,50085,401
85,26663,87591,441
107,635
161,605
128,682
115,000
85,000997,747
TBD

13,754
34,58825,50085,401
85,26663,87591,407
107,669
161,605
128,682
115,000
85,000997,747
TBD

Costs a6,169
24,23824,122
26,27846,052
84,321
99,215110,074
153,368
105,908
139,984
143,828
963,557
TBD

Costs through FY 2015 reflect actual costs; costs for FY 2016 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 2016 Hardware funding amount.
Science/Fusion Energy Sciences/
14-SC-60, U.S. Contributions to ITER
FY 2017 Congressional Budget Justification
170
b

a

Cash Contributions
FY 2006
FY 2007
FY 2008
FY 2009
FY 2010
FY 2011
FY 2012FY 2013
FY 2014b
FY 2015
FY 2016 b
FY 2017
Subtotal
Total, Cash Contributions
Total, TEC
Other project costs (OPC)FY 2006
FY 2007
FY 2008
FY 2009
FY 2010
FY 2011
FY 2012 c
FY 2013a
FY 2014ad
FY 2015
FY 2016
FY 2017
Subtotal
Total, OPC
Total Project Costs (TPC)FY 2006
FY 2007
FY 2008
FY 2009
FY 2010
FY 2011
FY 2012a
FY 2013a
FY 2014aba(dollars in thousands)
Appropriations
Obligations

Costs a

2,112
7,412
2,644
23,59929,734
3,125
13,214
13,80532,895
15,957040,000184,497
TBD
TBD

2,112
7,412
2,644
23,59929,734
3,125
13,214
13,80532,895
15,957040,000184,497
TBD
TBD

2,112
7,412
2,644
23,59929,734
3,125
13,214
13,80532,895
15,957040,000184,497
TBD
TBD

3,449
18,000-2,07415,00020,00013,000
345
2,560
5,000
5,361
0
0
80,641TBD

3,449
18,000-2,07415,00020,00013,000
345
2,560
5,000
5,361
0
0
80,641
TBD

1,110
7,607
7,513
5,072
7,754
10,032
22,336
5,984
2,717
5,500
5,016
0
80,641
TBD

19,31560,00026,070124,000
135,000
80,000105,000
124,000
199,500

19,31560,00026,070124,000
135,000
80,000104,966
124,034
199,500

9,391
39,25734,27954,94983,54097,478
134,765
129,863
188,980

Includes cash payments, secondees, taxes and tax support.
No FY 2016 funding is provided to support the ITER organization.
c
Prior actuals adjusted to incorporate project funds utilized at PPPL and DOE. Obligation adjusted to reflect year-end PPPL
settlement funding.
dPrior 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.
Science/Fusion Energy Sciences/
14-SC-60, U.S. Contributions to ITER
171
FY 2017 Congressional Budget Justificationb(dollars in thousands)
Appropriations
Obligations
Costs a150,000
150,000
127,365
115,000
115,000
145,000
125,000
125,000
183,828
1,262,885
1,262,885
1,228,695
TBD
TBD
TBD

FY 2015
FY 2016
FY 2017
Subtotal
Total, TPC
6.

Details of the 2017 Project Cost Estimate

Since CD-1, it has not been possible to baseline the project because of continued delays in the international ITER
construction schedule; therefore a Total Project Cost estimate cannot be formulated at this point in time. Until such time as
CD-2 can be approved, U.S. funding will be managed to address annual project priorities and to allow flexibility to adapt tothe changing state of the project.
7.

Schedule of Appropriation Requests

RequestYear
FY 2006 TEC
OPC
TPC
FT 2007 TEC
OPC
TPC
FY 2008 TEC
OPC
TPC
a
FY 2009 TEC
OPC
TPC
FY 2010 TEC
OPC
TPC
FY 2011 TEC
OPC
TPC
FY 2012 b TEC
OPC
TPC
FY 2013 c TEC
OPC
TPC

a

Prior
Years
889,000
74,400963,400
800,151
44,949845,100
801,330
43,770845,100
266,366
38,075
304,441
294,366
70,019364,385
379,366
65,019444,385
304,566
60,019364,385
371,366
73,019444,385(dollars in thousands)
FY 2012120,000
6,200
126,200
130,0000
130,000
130,0000
130,000
0
0
0
0
0
0
0
0
0
90,00015,000105,000
104,93070
105,000

FY 2013
29,0003,400
32,400116,900
0116,900
116,900
0116,900
0
0
0
0
0
0
0
0
0
0
0
0
140,965
9,035
150,000

FY 201400030,000030,00030,000030,000
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0

FY 2015
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0

FY 2016
0
0
0
0
0
0
0
0
0
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD

FY 2017 Outyears
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
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
TBD
TBD
TBD
TBD
TBD
TBD

Total
1,038,000
84,0001,122,000
1,077,051
44,9491,122,000
1,078,230
43,7701,122,000
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
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 2010.
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.
Science/Fusion Energy Sciences/
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172

Request
Year
FY 2014 a TEC
OPC
TPC
FY 2015 TEC
OPC
TPC
FY 2016 TEC
OPC
TPC
FY 2017a TEC
OPC
TPC
8.

Prior
Years
371,366
73,019444,385
377,010
67,375444,385
377,010
67,375444,385
377,010
67,375444,385(dollars in thousands)
FY 2012104,93070
105,000
104,93070
105,000
104,93070
105,000
104,93070
105,000

FY 2013
105,57270
105,642
121,465
2,535
124,000
121,465
2,535
124,000
121,499
2,535
124,034

FY 2014225,0000
225,000
194,500
5,000
199,500
194,500
5,000
199,500
194,500
5,000
199,500

FY 2015000144,6395,361
150,000
144,6395,361
150,000
144,6395,361
150,000

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

FY 2017 Outyears
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
125,0000
TBD
125,000
TBD

Total
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD
TBD

Related Operations and Maintenance Funding Requirements

The U.S. Contributions to ITER operations is assumed to begin with initial integrated commissioning activities and continue
for a period of 15 to 25 years. The fiscal year in which commissioning activities begin depends on the international ITER
project schedule and is therefore TBD.
Start of Operation or Beneficial Occupancy (fiscal quarter or date)
Expected Useful Life (number of years)
Expected Future start of D&D for new construction (fiscal quarter)
9.

TBD
15–25
TBD

D&D Funding Requirements

Since ITER is being constructed in France by a coalition of countries and will not be a DOE asset, the “one-for-one”
requirement is not applicable to this project.
The U.S. Contributions to ITER Decommissioning are assumed to begin when operations commence and continue for aperiod of 20 years. The U.S. is responsible for 13 percent of the total decommissioning cost.
The U.S. Contributions to ITER Deactivation are assumed to begin 20 years after commissioning and continue for a period of
5 years. The U.S. is responsible for 13 percent of the total deactivation cost.
10. Acquisition Approach for US Hardware Contributions
The USITER Project Office (USIPO) at Oak Ridge National Laboratory, with its two partner laboratories (Princeton Plasma
Physics Laboratory and Savannah River National Laboratory), will procure and deliver in-kind hardware in accordance with
the Procurement Arrangements established with the International Organization (IO).
The USIPO will subcontract with a variety of research and industry sources for design and fabrication of its ITER
components, ensuring that designs are developed that permit fabrication, to the maximum extent possible, under fixedprice subcontracts (or fixed-price arrangement documents with the IO) based on performance specifications, or more rarely,
on build-to-print designs. USIPO will use cost-reimbursement type subcontracts only when the work scope precludes
accurate and reasonable cost contingencies being gauged and established beforehand.

aPrior to FY 2015, the requests were for a major item of equipment broken out by TEC, OPC, and TPC.
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FY 2017 Congressional Budget Justification

USIPO will utilize best value, competitive source selection procedures to the maximum extent possible, including foreign
firms on the tender/bid list where appropriate. Such procedures shall allow for cost and technical trade-offs during source
selection.
For the large-dollar-value subcontracts (and critical path subcontracts as appropriate), USIPO will utilize unique subcontract
provisions to incentivize cost control and schedule performance.
In addition, where it is cost effective and it reduces risk, the USIPO will participate in common procurements led by the IO,
or request the IO to perform activities that are the responsibility of the U.S.

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FY 2017 Congressional Budget Justification