Research Needs for Magnetic Fusion Energy Sciences - US Burning ...

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thrust 13: Establish the science and technology for fusion power extraction and tritium sustainability. Fusion must create the tritium fuel it uses, and do so in the same systems that capture and extract the fusion energy. This Thrust develops the scientific foundation and engineering of practical, safe and reliable processes and components that harvest the heat, create and extract the tritium, and rapidly process and contain the tritium. The Thrust will culminate in a fuel and power handling capability on a scale needed for a demonstration energy system. thrust 14: Develop the material science and technology needed to harness fusion power. The objective of this Thrust is to create low-activation, high-performance materials that effectively function for a long time in the hostile fusion environment. an essential requirement to fulfill the mission of this Thrust is the establishment of a fusion-relevant neutron source to perform accelerated characterization of the effects of radiation damage to materials. thrust 15: Create integrated designs and models for attractive fusion power systems. advanced design studies, focused primarily on demo, but also on nearer term fusion nuclear facilities, is one element of this Thrust. These would lay out the scientific basis for fusion power and provide focus to the research efforts required to close the knowledge gap to demo. The other element comprises science-based predictive modeling capabilities for plasma chamber components and related systems. Theme 5: opTimizing The magneTiC ConfiguraTion currently most large fusion experimental devices are based on the tokamak magnetic configuration, a design using a strong, axisymmetric external magnetic field to achieve operating parameters close to those in a fusion reactor. alternative magnetic configurations are studied to investigate physics and technology principles that could optimize the design of future fusion devices. The most developed alternate toroidal magnetic configurations are considered in Theme 5. thrust 16: Develop the spherical torus to advance fusion nuclear science. experiments on the small aspect ratio tokamak, or spherical torus, would be extended to regimes of lower collision frequency, approaching values needed for fusion nuclear science applications. Plasma startup, power handling, controlled stability, and sustainment issues in this regime would be studied in long-pulse experiments using stronger magnetic fields, improved heating and current drive, and advanced diagnostics, with strong coupling to theory and modeling. thrust 17: Optimize steady-state, disruption-free toroidal confinement using 3-D magnetic shaping, and emphasizing quasi-symmetry principles. magnetic quasi-symmetry in 3-d configurations is expected to lead to excellent plasma confinement while ensuring stable steady-state burning plasma performance with minimal need for control. This Thrust would conduct new quasi-symmetric experiments, which would, together with theory, engineering design, and targeted international collaboration, validate extrapolation to burning plasma applications. 12
thrust 18: achieve high-performance toroidal confinement using minimal externally applied magnetic field. This Thrust advances a multi-faceted program of theory, simulation, and well-diagnosed experiments to resolve critical issues of confinement, stability, and current sustainment in magnetic configurations with minimal toroidal field. new devices with heating and current drive systems would enable scaling to high temperature and small ion gyroradius. Fusion system studies will guide productive directions for present and future research. 13
Page 1 and 2: Research Needs for Magnetic Fusion
Page 3: Research Needs for Magnetic Fusion
Page 7 and 8: ExEcutivE SuMMaRy nuclear fusion
Page 9 and 10: Magnetic confinement magnetic confi
Page 11 and 12: The thrusts span a wide range of si
Page 13: eactor, most heat comes from fusion
Page 17 and 18: confinement is measured by the so-c
Page 19: PART I: ISSUES AND RESEARCH REQUIRE
Page 22 and 23: ReneW Organization: Themes The stru
Page 24 and 25: 22 Table 1. ReNeW Thrusts Address R
Page 26 and 27: ON PREVIOUS PAGE Nonlinear simulati
Page 28 and 29: extended operation phase. The optim
Page 30 and 31: Figure 2. Alpha particles can cause
Page 32 and 33: Figure 3. Spectrogram of the time-v
Page 34 and 35: Do the alpha particles couple to th
Page 36 and 37: • improved understanding of the e
Page 38 and 39: most relevant to iteR. Recent obser
Page 40 and 41: H-mode access: access to the h-mode
Page 42 and 43: although present-day devices have m
Page 44 and 45: estimates indicate that it will be
Page 46 and 47: can enter the plasma core and dimin
Page 48 and 49: ent drive alone cannot account for
Page 50 and 51: Figure 10. Control involves the ele
Page 52 and 53: to operation of iteR. solutions for
Page 54 and 55: • identification and stabilizatio
Page 56 and 57: Disruption prediction accurate pred
Page 58 and 59: Figure 12. The application of non-a
Page 60 and 61: ion losses, a quantitative predicti
Page 62 and 63: due to incompatibility of the measu
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agnostic measurements of critical p
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quires assessment of when potential
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suggesTions for furTher reading 1.
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miTigaTing TransienT eVenTs in a se
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ON PREVIOUS PAGE Nonlinear simulati
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increasing power density and pulse
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of recent accomplishments that have
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ity limits have been maintained. in
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highly risky in such an environment
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proximity-coil-based magnetics is ~
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will dominate the external sources
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The barrier gradient is generally l
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interaction with plasma boundary an
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itER-at aRiES-i aRiES-at b n (%) 3.
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and morphology, are needed. new mea
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field and temperature fluctuations
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large-scale process control problem
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tics. integrated control methods fo
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ing and design include computationa
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dated in the corresponding structur
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These requirements are applicable t
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• assess computationally, on test
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Research Requirements for Electron
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the launcher design is partly “tr
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tunities and goals for a few of the
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front layers of the field magnets c
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R&D Strategy a number of critical t
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formance burning plasmas are covere
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CreaTing prediCTaBle, high-performa
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magneTs JosePh mineRvini, massachus
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ON PREVIOUS PAGE Design of the ITER
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to stabilize deleterious plasma mod
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longer than the (solid) thermal equ
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Promising new ideas have been devel
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to handle 10 mW/m 2 , and elms with
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• liquid surface PFc operation in
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integrated effort that includes fun
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Taming The plasma-maTerial inTerfaC
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138
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ON PREVIOUS PAGE Design of an ITER
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trons in the breeding blanket. Thes
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Safety and Environment • developm
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plasma and gas to the scrape-off la
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gaps: need to select and test the t
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• neutron and other radiation tra
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emphasis on modeling and expertise
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gap: Current understanding of stren
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Research needs critical research ne
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• Proposing integrated safety des
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• techniques and instruments to a
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Qualifying DEMO Components Possible
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• developing the design of an eff
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harnessing fusion power Theme memBe
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168
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ON PREVIOUS PAGE Reconstruction of
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Figure 1. Configuration space for t
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of 40%.) localized instabilities (t
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• Reduction of spheromak magnetic
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ment, but also micro- and macro-ins
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esearch requirements • evaluate t
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the banana regime, low turbulent tr
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in stellarator discharges with ohmi
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• investigate how demountable coi
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tion using a central solenoid is al
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functions, edge flows, and edge neu
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Development of predictive capabilit
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Edge localized modes (ELMs): edge l
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theory predictions for alfvén inst
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coils, to permit replacement of the
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stand the relative roles of long-to
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Table 1. 202
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primarily electrostatic, in the cas
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to be important in present experime
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PLaSMa bOunDaRy intERaCtiOnS The ex
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calized field errors that can cause
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needed Theory, Computation, Modelin
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Scientific Issues and research requ
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esearch requirements new facilities
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small, concept exploration experime
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tRanSPORt: DEtERMinE unDERLying tRa
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esearch requirements analysis of ne
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nEEDED FaCiLitiES nEEDED tHEORy, CO
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connections Between Research Requir
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opTimizing The magneTiC ConfiguraTi
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230
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232
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234
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Proposed actions: • Prioritize bu
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3) as planning matures for the rese
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that have high impact, that benefit
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could have an impact on the identif
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The Us fusion program is well posit
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Mitigation of disruptions in the ev
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elevant plasmas for very long pulse
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and stability, and mitigation requi
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• control alpha heating feedback
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heavy ion beam probes (already in u
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alpha particles (ash removal). mode
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• determine minimum heating power
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Research should focus on developing
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estal structure need to be coupled
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• sufficient heating with little
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Proposed actions: Short-term: begin
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Demonstrate active control of the p
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Demonstrate burn control and contro
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Develop the means for and demonstra
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Medium-term: Test and optimize full
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276
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• Recruit, train and support dedi
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With this information in hand, phys
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to carry out the validation program
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and new devices could be designed w
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• high-field sc magnets for stead
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Element 2 — High current conducto
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Element 7 — integration of conduc
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many other scientific fields are be
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• based on these assessments, pro
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systems include neutral beams, ion
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The Us d-t facility, studied in 1b,
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300
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• design and implement innovation
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the controlling instabilities and s
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cross-field transport in the pedest
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The modeling of near-surface plasma
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310
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• build large-size test stands wh
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trol of the energy, impact angle, a
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ties that take advantage of simple
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ased materials development with adv
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introduction Thrust 11 addresses th
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technology is now evolving to inclu
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The elements of a thrust to develop
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The plasma facing components in a d
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to demonstrate that steady and tran
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mum of nuclear activation and prese
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332
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introduction harnessing fusion powe
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each Thrust 13 element includes the
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Figure 3. System concept for perfor
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equirements. Understanding the fuel
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• Use a combination of existing a
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chemical interactions between the s
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dose fusion-relevant environment wi
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Use a combination of existing and n
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350
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evaluate, through advanced design a
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at the time when the demo design is
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3. Computational analysis managemen
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Materials and Components: Fuel Cycl
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• employ energetic particle beams
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• develop and validate theoretica
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• develop new diagnostics for int
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• increase sustained noninductive
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368
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Proposed actions: 1. conduct two qu
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The key areas in which new knowledg
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• exploration of high-temperature
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• availability of high-power radi
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378
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• study FRc stability at small io
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techniques for integrated data anal
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4. based on the outcome of actions
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2. With information from action 1,
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388
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aCROnyMS anD abbREViatiOnS (continu
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aPPENdix c: tHEME WoRKSHoPS tHEME W
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14. d.l. humphreys, Active Realtime
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tHEME 2: CREating PREDiCtabLE HigH-
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43. t.W. Petrie, White Paper: Some
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tHEME 3: taMing tHE PLaSMa MatERiaL
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37. e.J. strait, J.c. Wesley, m.J.
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20. s.a. maloy and e. Pitcher, Fusi
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tHEME 5: OPtiMizing tHE MagnEtiC CO
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39. P.W. terry, a. boozer, J.s. sar
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don coRRell, lawrence livermore nat
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GeoRGe mckee, University of Wiscons
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tony tayloR, General atomics RichaR
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