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

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tHEME 2: CREating PREDiCtabLE HigH-PERFORManCE StEaDy-StatE PLaSMaS 1. l.R. baylor, Fusion Burn Control with Isotopic Fueling 2. R.l. boivin, J.c. deboo, and R.k. Fisher, A Fusion Development Facility to Develop, Field, and Test Diagnostic Solutions for DEMO 3. a. boozer, G.h. neilson, and m. zarnstorff, Non-Axisymmetric Shaping as a Research Thrust 4. R.J. buttery, Disruptions – Research Needs 5. R.J. buttery, The Need for a Fusion Science Integration Experiment in the US 6. P. cadaret, Advanced Data Compression Methods (ADCM) 7. P. cadaret, Complex Model Acceleration Using Neural Networks 8. P. cadaret, Empirically Trained Diagnostic Systems (ETDS) 9. v.s. chan, Validated Theory and Predictive Modeling 10. d.a. d’ippolito and J.R. myra, ICRF-Edge and Surface Interactions 11. edge coordinating committee (ecc), Integrated Edge-Plasma and Plasma-Wall Interaction Research 12. l. el-Guebaly and R. Raffray, Impact of Tritium Breeding on Design Implications to Withstand Disruptions and Runaway Electrons 13. l. el-Guebaly, Need for High Tritium Burn-up Fraction in Plasma to Relax Tritium Breeding Requirement for Demo and Fusion Power Plants 14. t.e. evans, Edge Localized Mode and pedestal control using resonant magnetic perturbation coils 15. J. Ferron, Global parameter control in ITER and a steady-sate DEMO: a white paper for ReNeW 16. J. Ferron, Profile control in a steady-state advanced tokamak: a white paper for ReNeW 17. a.m. Garofalo, Integration of High Performance, Steady-State Burning Plasmas 18. d.a. Gates, Integrated stability control 19. d.a. Gates, Research gaps for reactor startup sequencing in the ITER era 20. R.J. Goldston, The Role of a Long-Pulse, High-Heat-Flux, Hot-Walls Confinement Experiment in the Study of Plasma-Wall Interactions for CTF and Demo 21. R.J. Goldston, The Role of a Long-Pulse, High-Heat-Flux, Hot-Walls Confinement Experiment in the Development of Plasma Facing Components for CTF and Demo 22. R.J. Goldston, Requirements for a Confinement Device with a Goal to Develop Tritium Breeding Blanket Modules, Based on FESAC Fusion Development Path Plan 400
23. l.R. Grisham, Neutral Beam Development Plans and Needs for ITER 24. J. harris, Perspectives for operation of stellarators as fusion reactors 25. d.l. humphreys, Active Realtime Control Issues and Role of a Fusion Development Facility 26. y. in, m. okabayashi, e.J. strait, h. Reimerdes, and R.J. la haye, Holistic approach against performance-limiting instabilities in steady state plasmas, 27. t.P. intrator and R.P majeski, Radio frequency sustainment and current drive for Compact Tori 28. m. kotschenreuther, s.m. mahajan, P. valanju, J.m. canik, a.m. Garofalo, b. labombard, and R. maingi, Severe divertor issues on next step devices, and validating the Super-X divertor as a promising solution 29. a.h. kritz, R. budny, and G. bateman, Open Issues for Integrated Modeling 30. R.J. la haye, Issue: Tearing Mode Avoidance and Stabilization 31. k.c. lee, Modeling of Turbulence Diffusion and H-mode Transition including Poloidal Momentum Exchange from Ion-Neutral Collisions 32. J. leuer and d. humphreys, Solenoidless Startup Research Thrusts for Tokamaks 33. m.a. makowski, d.d. Ryutov, a. hyatt, t.h. osborne, and m.v. Umansky, White Paper: Control of a Snowflake divertor 34. J. manickam, Development of a Stability Dashboard for Tokamaks 35. d. meade, Scientific Issues and Gaps for High-Performance Steady-State Burning-Plasmas 36. J. menard and R. J. Goldston, Contributions of NHTX to high-performance steady-state plasma development 37. J. v. minervini, l. bromberg, d. c. larbalestier, m. Gouge, b. e. nelson, R. J. Thome, and Gianluca sabbi, US Fusion Program Issues and Requirements for Superconducting Magnets Research 38. R. moyer, t. e. evans, R. Groebner, h. Reimerdes, and P. snyder, Pedestal Optimization for Confinement and ELM Control 39. J.R. myra and d.a. d’ippolito, Comments on Verification and Validation in Edge Research 40. R.e. nygren, Future Plasma Facing Components (PFCs) & In-vessel Components (IVCs): Strengthened Sustained and Integrated Approach for Modeling and Testing HHFCs 41. R.e. nygren, In-vessel Engineering Instrumentation for Future Fusion Devices 42. k. owens, Burning Plasma Control 401
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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
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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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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,
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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 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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