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

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nEEDED FaCiLitiES nEEDED tHEORy, CODES ExiSting tHEORy, CODES (b) intEgRatED PHySiCS ExP. HigH-S ExPERiMEnt ExiSting COnCEPt- ExPLORatiOn FaCiLitiES (a) FRC iSSuES extend physics; verify & validate codes, explain & predict exp. nonlinear, resistive, & hall mhd, hybrid; Pic, prolate & oblate geom. extend stability to higher-flux, larger size FRc 20-50 mWb flux FRc: stability phys. (kinetic ions, shear flow, etc.) Generate & sustain using RmF, mergingspheromaks,thetapinches; divertors and field-shaping effects StabiLity at LaRgE S model anomalous transport mechanisms in FRc Pic, hamiltonian symplectic neutral-beam and/or rf heating, diagnostics for micro-instab. transp. in high-s, stable, quasi-stationary FRc; transp. at low vd /vi transport in RmFformed and sustained FRcs and in pulsed FRcs tRanSPORt nonlinear, resistive, & hall mhd, hybrid; prolate & oblate geom., Pic nonlinear, resistive, & hall mhd, hybrid; prolate & oblate geom., Pic, hamiltonian symplectic steady-state sustainment; diagn. for current driven microinstab. tbd: nbi, RmF or other means RmF driven; stabilization by RmF fields, pulsed FRcs CuRREnt DRiVE anD SuStainMEnt 224 hybrid or kinetic codes, Pic betatron orbit electrons neutral beam injection neutral beam injection hybrid codes FaSt PaRtiCLES nonlinear, resistive, & hall mhd, hybrid codes with sources ohmic heating; test particle calculations for RmF stochastic heating RmF, neutral beams, radiofrequency, compression RmF, neutral beams, radiofrequency RmF, merging (reconnection), ohmic heating, theta pinch, compression HEating (A) Includes Colorado FRC, FRX-L, MRX, PFRC, PHD, PV Rotomak, SSX, TCS-U (B) Includes HYM, NIMROD, Hi-Fi, RMF-Hamiltonian, Symplectic, PIC Table 3.
nEEDED FaCiLitiES nEEDED tHEORy, CODES ExiSting tHEORy, CODES (b) intEgRatED PHySiCS ExP. SuSt. & COnF. ExPERiMEnt ExiSting COnCEPt- ExPLORatiOn FaCiLitiES (a) SPHEROMaK iSSuES 2-fluid simulation with kinetic effects; boundary cond. consistent with G-s fits to data, resistive mhd (rmhd) simulations extend best sustainment method to long-pulse, etc. high-power & vac.; test concepts from ce exp., simulations cW inductive helicityinjection, hel. inj. data base, inductive drive, efficiency study SuStainMEnt anD COnFinEMEnt plasmas 2-fluid simulation with kinetic effects; boundary cond. consistent with plasmas rmhd modeling, helicity balance extend best formation method to long-pulse, etc. high-power & vac.; test concepts from ce exp., simulations cW inductive helicity injection, inductive, multi-pulsed startup, gun-plasma coupling efficiency FORMatiOn combined macro- & microscopic phys.; integrate with FsP G-s fits to data, rmhd with collisional closure electron & ion transport; auxiliary heating; diagnostics electron transport data base for electron confinement tRanSPORt nonlin. 2-fluid simulation with kinetic effects G-s fits to data, linear and nonlin. rmhd, mercier limits Find and study beta limits; heating, diagnostics database on limiting beta, bow-tie geom. allows high mercier b limit 225 limits for various current drive methods bEta LiMitS integrate atomic physics and coupling to wall and other sources into codes n/a Wall cond., particle injection, dedicated exp. n/a Wall conditioning & gas injection, flows in helicity injection PaRtiCLE baLanCE anD DEnSity COntROL adapt energetic particle modeling n/a n/a neutral beam injection delta-f treatment FaSt PaRtiCLES extend RFP and tokamak analyses to spheromak n/a based on RFP & tokamak experience n/a n/a RESiStiVE WaLL MODES (A) Includes CalTech, DRX, HIT-SI MRX, PBX, SSPX (database only), SSX (B) Includes Corsica (Grad.-Shaf. based), NIMROD, Hi-Fi Table 4.
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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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Page 178 and 179: • Reduction of spheromak magnetic
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Page 188 and 189: • investigate how demountable coi
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Page 192 and 193: functions, edge flows, and edge neu
Page 194 and 195: Development of predictive capabilit
Page 196 and 197: Edge localized modes (ELMs): edge l
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Page 210 and 211: PLaSMa bOunDaRy intERaCtiOnS The ex
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Page 214 and 215: needed Theory, Computation, Modelin
Page 216 and 217: Scientific Issues and research requ
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Page 222 and 223: tRanSPORt: DEtERMinE unDERLying tRa
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Page 228 and 229: connections Between Research Requir
Page 230 and 231: opTimizing The magneTiC ConfiguraTi
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Page 238 and 239: Proposed actions: • Prioritize bu
Page 240 and 241: 3) as planning matures for the rese
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Page 248 and 249: Mitigation of disruptions in the ev
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Page 254 and 255: • control alpha heating feedback
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Page 260 and 261: • determine minimum heating power
Page 262 and 263: Research should focus on developing
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Page 268 and 269: Proposed actions: Short-term: begin
Page 270 and 271: Demonstrate active control of the p
Page 272 and 273: Demonstrate burn control and contro
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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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