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

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needed Theory, Computation, Modeling Existing Facilities needed Facilities Existing Theory, Computation, advanced Control MSt RFx CEs PE (itER-era goal) Modeling PoP issues 3-d nonlinear 2-fluid (s=108 ), gyrokinetics 3-d nonlinear mhd, test-particle stochastic theory establish base for burning-plasma experiment with ip≥4 ma single-helicity state at low aspect current profile control, S-scaling, singlehelicity state, at ip≥2 ma S-scaling, singlehelicity state, at ip 1 perpendicular beam injection, vi /va≤1 tangential beam injection, substantial fast ion beta, vi /va≥1 Energetic particle effects 3-d nonlinear 2-fluid 3-d nonlinear mhd with finite pressure verify and control at high performance identify at i p ≥2 ma limited capability possible with further improved confinement possibly identify at ip
thE coMpact toRuS: FRc aNd SphERoMak introduction The mission of compact torus (ct) research is to: Develop a compact magnetic fusion reactor without toroidal field coils or a central solenoid. Progress in this mission is supported by the iteR-era goal established by taP: To demonstrate that a CT with a simply connected vessel can achieve stable, sustained or long pulsed plasmas at kilovolt temperatures, with favorable confinement scaling to proceed to a pre-burning CT plasma experiment. a ct has a toroidal magnetic and plasma geometry, but is contained within a simply connected vacuum vessel such as a cylinder or sphere. spheromaks and field-reversed configurations fall into this category. compact tori have high plasma and engineering betas, potentially obtaining highpower density at relatively low magnetic fields. The primary benefit of cts for fusion is the absence of toroidal field coils, simplifying solutions to many engineering problems. studying highbeta, fusion-relevant plasma in simply connected geometries affords both physics and technology opportunities not found in other configurations, in a program in which the Us is the world leader. The ct program currently consists of experiments at the concept exploration level, involving both the spheromak and the FRc, and other hybrid configurations may be possible. ct funding has traditionally been a small part of the alternate concepts program, but both the spheromak and FRc configurations have made substantial plasma physics progress in recent years, pointing the way to future research on ct science and technology opportunities. Axial-eld bias coils Figure 6. On the left is the field-reversed configuration and on the right is the spheromak configuration. No physical structure links the plasma torus in these configurations. 213 Spheromak plasma with magnetic eld lines Flux Conserver
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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
Page 164 and 165: Qualifying DEMO Components Possible
Page 166 and 167: • developing the design of an eff
Page 168 and 169: harnessing fusion power Theme memBe
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Page 172 and 173: ON PREVIOUS PAGE Reconstruction of
Page 174 and 175: Figure 1. Configuration space for t
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Page 178 and 179: • Reduction of spheromak magnetic
Page 180 and 181: ment, but also micro- and macro-ins
Page 182 and 183: esearch requirements • evaluate t
Page 184 and 185: the banana regime, low turbulent tr
Page 186 and 187: in stellarator discharges with ohmi
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
Page 198 and 199: theory predictions for alfvén inst
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Page 202 and 203: stand the relative roles of long-to
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Page 210 and 211: PLaSMa bOunDaRy intERaCtiOnS The ex
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Page 216 and 217: Scientific Issues and research requ
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Page 222 and 223: tRanSPORt: DEtERMinE unDERLying tRa
Page 224 and 225: esearch requirements analysis of ne
Page 226 and 227: nEEDED FaCiLitiES nEEDED tHEORy, CO
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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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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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