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

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aCROnyMS anD abbREViatiOnS (continued) Diii-D a tokamak at Ga DOE department of energy D-t deuterium-tritium (plasma-fuel interaction) —————————————————————————————————————————————— EaSt experimental advanced superconducting tokamak in china EbW electron bernstein Wave ECCD electron cyclotron current drive ECDC electron cyclotron discharge cleaning ECE electron cyclotron emission ECH electron cyclotron heating ECRF electron cyclotron Range of Frequencies EDa enhanced da mode EDgE2D a two-dimensional plasma-fluid transport code ELM edge localized mode EP energetic Particle EPM energetic Particle mode EPRi electric Power Research institute ESEL an edge plasma turbulence simulation code Etg electron temperature Gradient Eu european Union eV electron volt Extrap-t2R Reversed field pinch experiment at the Royal institute of technology, sweden —————————————————————————————————————————————— FaCEtS computational modeling framework FCi Flow channel insert FESaC Fusion energy sciences advisory committee FLR Finite larmor Radius FnSF Fusion nuclear science Facility Fr Failure rate FRC Field-reversed configuration FRx-L a field-reversed configuration plasma source at lanl FSP Fusion simulation Program FtE Full time equivalent Ftu Frascati tokamak Upgrade, a tokamak in italy FzK Research center in karlsruhe, Germany —————————————————————————————————————————————— ga General atomics, california gaE Global alfvén eigenmode gEnE a simulation code gHz Gigahertz gPi Gas Puff imaging gW Gigawatt —————————————————————————————————————————————— HDH high-density h-mode HHFW high harmonic Fast Wave Hi (magnetic) helicity injection HibP heavy ion bean Probe Hit-Si steady inductive helicity injected torus at the University of Washington, seattle H-Mode high-confinement mode HSx helically symmetric experiment, a stellarator at the University of Wisconsin-madison HtS high-temperature superconductors HyM a numerical simulation code 390
aCROnyMS anD abbREViatiOnS (continued) —————————————————————————————————————————————— ibW ion bernstein Wave iCRF ion cyclotron Range of Frequencies iCW ion cyclotron Wave iFMiF international Fusion materials irradiation Facility inL idaho national laboratory, idaho itb internal transport barrier itER international burning plasma experiment being built in cadarache, France itg ion-temperature Gradient mode itPa international tokamak Physics activity —————————————————————————————————————————————— jaEa Japan atomic energy agency jaERi Japan atomic energy Research institute jEt european tokamak sited in the Uk jt-60Sa Japanese tokamak-super advanced (under construction) at JaeRi jt-60u Japanese tokamak-Upgrade at JaeRi —————————————————————————————————————————————— ka kiloampere KbM kinetic ballooning mode keV kiloelectron volt KStaR korea superconducting tokamak advanced Research device in south korea kV kilovolt —————————————————————————————————————————————— low-a low aspect ratio LanL los alamos national laboratory, new mexico LanL-DRx a spheromak experiment at lanl LDx levitated dipole experiment at mit LH lower hybrid L-H low-to-high-confinement mode (transition) LHCD lower hybrid current drive LHD large helical device, a stellarator experiment in Japan LHRF lower hybrid Radiofrequency Li lithium LLnL lawrence livermore national laboratory, california L-mode low-confinement mode LSx large-S experiment, a field-reversed configuration experiment at the University of Washington, seattle LtS low-temperature superconductor Ltx lithium tokamak experiment at PPPl —————————————————————————————————————————————— Ma megampere MaRS a computational code MaSt mega ampere spherical tokamak at culham laboratory, Uk MaSt-u mega ampere spherical tokamak-Upgrade at culham laboratory, Uk MCCD mode conversion current drive MCH mode conversion heating MELCOR a safety analysis computer code MeV mega electron volt MFE magnetic Fusion energy MHD magnetohydrodynamics Mit massachusetts institute of technology, massachusetts MHz megahertz 391
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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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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
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
Page 348 and 349: dose fusion-relevant environment wi
Page 350 and 351: Use a combination of existing and n
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Page 354 and 355: evaluate, through advanced design a
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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,
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Page 394 and 395: aCROnyMS anD abbREViatiOnS (continu
Page 396 and 397: 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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