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

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aPPENdix a: acRoNyMS aNd aBBREviatioNS 2-D two-dimensional 3-D Three-dimensional 4-D Four-dimensional —————————————————————————————————————————————— aC alternating current aE alfvén eigenmode aLPS advanced liquid Plasma-facing surface Program (doe Program) aPEx advanced Power extraction Program (doe Program) aPS american Physical society aPS/DPP american Physical society/division of Plasma Physics aRiES advanced Reactor innovation evaluation studies aRiES-at aRies-advanced tokamak design aRiES-RS aRies Reverse shear design aRiES-CS aRies compact stellarator design aSDEx a tokamak experiment at max-Planck institute, Germany aSME american society of mechanical engineers at advanced tokamak aug asdeX-Upgrade, a tokamak in Germany aWCD alfvén Wave current drive aWH alfvén Wave heating —————————————————————————————————————————————— b magnetic field b2-Eirene a two-dimensional plasma-fluid transport code bES office of basic energy sciences, department of energy bES beam emission spectroscopy bOut an edge plasma turbulence simulation code bR breeding Ratio bSCCO-2212 a high-temperature superconductor material —————————————————————————————————————————————— CaD computer-aided design CaE compressional alfvén eigenmode CE concept exploration CER charge exchange Recombination (spectroscopy diagnostic) CFC carbon Fiber composite CHi coaxial helicity injection CiCC cable-in-conduit-conductor C-Mod (or alcator c-mod) a tokamak at the mit Plasma science and <strong>Fusion</strong> center Colorado FRC colorado Field-Reversed configuration CPES center <strong>for</strong> Plasma edge simulation Ct compact torus CtF component test Facility CtH a compact stellarator-tokamak hybrid at auburn University in alabama Ctx a spheromak experiment (operations ended) at lanl CW continuous Wave —————————————————————————————————————————————— DaLFti an edge plasma turbulence simulation code DC direct current DCLL dual coolant lead lithium D-D deuterium-deuterium (plasma-fuel interaction) DEbS a simulation code DEMO demonstration fusion power plant 389
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Research Needs for Magnetic Fusion
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Research Needs for Magnetic Fusion
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ExEcutivE SuMMaRy nuclear fusion
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Magnetic confinement magnetic confi
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The thrusts span a wide range of si
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eactor, most heat comes from fusion
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thrust 18: achieve high-performance
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confinement is measured by the so-c
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PART I: ISSUES AND RESEARCH REQUIRE
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ReneW Organization: Themes The stru
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22 Table 1. ReNeW Thrusts Address R
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ON PREVIOUS PAGE Nonlinear simulati
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extended operation phase. The optim
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Figure 2. Alpha particles can cause
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Figure 3. Spectrogram of the time-v
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Do the alpha particles couple to th
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• improved understanding of the e
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most relevant to iteR. Recent obser
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H-mode access: access to the h-mode
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although present-day devices have m
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estimates indicate that it will be
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can enter the plasma core and dimin
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ent drive alone cannot account for
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Figure 10. Control involves the ele
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to operation of iteR. solutions for
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• identification and stabilizatio
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Disruption prediction accurate pred
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Figure 12. The application of non-a
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ion losses, a quantitative predicti
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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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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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• 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
Page 340 and 341: Figure 3. System concept for perfor
Page 342 and 343: equirements. Understanding the fuel
Page 344 and 345: • Use a combination of existing a
Page 346 and 347: chemical interactions between the s
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Page 350 and 351: Use a combination of existing and n
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Page 354 and 355: evaluate, through advanced design a
Page 356 and 357: at the time when the demo design is
Page 358 and 359: 3. Computational analysis managemen
Page 360 and 361: Materials and Components: Fuel Cycl
Page 362 and 363: • employ energetic particle beams
Page 364 and 365: • develop and validate theoretica
Page 366 and 367: • develop new diagnostics for int
Page 368 and 369: • increase sustained noninductive
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Page 372 and 373: Proposed actions: 1. conduct two qu
Page 374 and 375: The key areas in which new knowledg
Page 376 and 377: • exploration of high-temperature
Page 378 and 379: • availability of high-power radi
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Page 382 and 383: • study FRc stability at small io
Page 384 and 385: techniques for integrated data anal
Page 386 and 387: 4. based on the outcome of actions
Page 388 and 389: 2. With information from action 1,
Page 392 and 393: aCROnyMS anD abbREViatiOnS (continu
Page 398 and 399: aPPENdix c: tHEME WoRKSHoPS tHEME W
Page 400 and 401: 14. d.l. humphreys, Active Realtime
Page 402 and 403: tHEME 2: CREating PREDiCtabLE HigH-
Page 404 and 405: 43. t.W. Petrie, White Paper: Some
Page 406 and 407: tHEME 3: taMing tHE PLaSMa MatERiaL
Page 408 and 409: 37. e.J. strait, J.c. Wesley, m.J.
Page 410 and 411: 20. s.a. maloy and e. Pitcher, Fusi
Page 412 and 413: tHEME 5: OPtiMizing tHE MagnEtiC CO
Page 414 and 415: 39. P.W. terry, a. boozer, J.s. sar
Page 416 and 417: don coRRell, lawrence livermore nat
Page 418 and 419: GeoRGe mckee, University of Wiscons
Page 420 and 421: tony tayloR, General atomics RichaR
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