dtic-frc-propulsion-network-analysis

AUGUST 1998 1999 – 2003 GA–A22950 QTYUIOP by PROJECT STAFF GA–A22950 THE DIII–D FIVE-YEAR PROGRAM PLAN 1999–2003 by PROJECT STAFF ABRIDGED VERSION This is an abridged version of the DIII–D Five-Year Technical Proposal. Not included are sections which include resumes, past publications and GA management structure. Work prepared under Contract Nos. DE-AC03-89ER51114, W-31-109-ENG-38, W-7405-ENG-36, W-7405-ENG-48, DE-AC05-96OR22464, DE-AC02-76CH03073, DE-AC04-94AL85000, and Grant Nos. DE-FG02-89ER53297, DE-FG02-86ER53223, DE-FG03-89ER51116, DE-FG03-86ER53266, DE-FG03-86ER53225, DE-FG03-95ER54294, DE-FG05- 96ER64373, and DE-FG03-97ER54415 for the U.S. Department of Energy GA PROJECT 3466 AUGUST 1998 DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof. TABLE OF CONTENTS 1.0 THE DIII–D FIVE-YEAR PROGRAM SUMMARY ....................................................................................1-1 1.0.1. The DIII–D National Program Overview and Mission ............................................................1-1 1.0.2. The Proposed DIII–D Five-Year Program Plan......................................................................1-2 1.0.3. Leadership ............................................................................................................................1-3 1.1. Tokamak Research Using the DIII–D National Facility .....................................................................1-5 1.1.1. Science Research ................................................................................................................1-9 1.1.2. DIII–D Facility Operations .....................................................................................................1-14 1.2. Upgrade DIII–D Components and Systems to Achieve Program Objectives ...................................1-19 1.2.1. ECH Upgrade ........................................................................................................................1-20 1.2.2. Divertor Upgrade ...................................................................................................................1-21 1.2.3. Magnet Pulse Length Upgrade..............................................................................................1-22 1.2.4. Upgrade Contingency Options .............................................................................................1-23 2.TECHNICAL DISCUSSION: THE DIII–D FIVE-YEAR PROGRAM PLAN .............................................2.1-1 2.1. The DIII–D Five-Year Program Plan .................................................................................................2.1-1 2.1.1. The DIII–D Mission ...............................................................................................................2.1-1 2.1.2. The DIII–D Program .............................................................................................................2.1-3 2.1.3. National Leadership ..............................................................................................................2.1-8 2.1.4. Benefits of DIII–D Research .................................................................................................2.1-8 2.1.5. The DIII–D National Team .................................................................................................... 2.1-10 2.2. The DIII–D Advanced Tokamak Program .........................................................................................2.2-1 2.2.1. The Plan ...............................................................................................................................2.2-1 2.2.2. What is an Advanced Tokamak? ..........................................................................................2.2-6 2.2.3. The Science, the Tools, and the Integration .........................................................................2.2-6 2.3. Fusion Energy Science in DIII–D ......................................................................................................2.3-1 2.3.1. Confinement Science and Transport Barrier Control ............................................................2.3-2 2.3.2. Stability Science ................................................................................................................... 2.3-20 2.3.3. Boundary Science ................................................................................................................ 2.3-35 2.3.4. Physics of Current Drive and Heating ..................................................................................2.3-62 2.4. Pathways to the Future......................................................................................................................2.4-1 2.4.1. The Path to ITER ...................................................................................................................2.4-1 2.4.2. The Path to an Optimized Superconducting Tokamak Power System ..................................2.4-7 2.4.3. The Path to a Compact Ignition Experiment ......................................................................... 2.4-13 2.4.4. The Path to the Spherical Tokamak Pilot Plant .................................................................... 2.4-15 2.4.5. Research Implications for DIII–D from a Look at Future Tokamak Possibilities ................... 2.4-18 General Atomics Report GA-A22950iii Project Staff THEDIII–D FIVE-YEARPROGRAMPLAN1999–2003 2.5. The DIII–D National Fusion Facility — Status and Upgrades............................................................2.5-1 2.5.1. Electron Cyclotron Heating and Current Drive Systems Upgrade ........................................ 2.5-14 2.5.2. Divertor System Upgrades ................................................................................................... 2.5-16 2.5.3. Magnet Pulse Length Upgrade (Baseline) ............................................................................ 2.5-21 2.5.4. Improvements to the DIII–D Tokamak (Completed as Part of Tokamak Research) ............. 2.5-23 2.5.5. Diagnostic Systems (Tokamak Research)............................................................................. 2.5-28 2.5.6. Control, Data Acquisition and Analysis Systems (Tokamak Research) ................................ 2.5-39 2.5.7. Fast Wave ICRF Systems (Option) ...................................................................................... 2.5-45 2.5.8. Neutral Beam Heating Systems ........................................................................................... 2.5-47 2.5.9. Other Upgrade Options ........................................................................................................ 2.5-50 2.6. The DIII–D National Fusion Program ................................................................................................2.6-1 2.6.1. National Leadership Role .....................................................................................................2.6-2 2.6.2. Collaborations and Outreach ................................................................................................2.6-3 2.6.3. The DIII–D National Team .................................................................................................... 2.6-20 2.6.4. DIII–D National Program Governance .................................................................................. 2.6-34 3.OTHER PERTINENT INFORMATION ......................................................................................................3-1 3.1. Development Process of the DIII–D Five-Year National Program Plan ............................................3-1 3.2. History and Accomplishments of the DIII–D Program........................................................................3-5 3.2.1. Origin of the Program ............................................................................................................3-5 3.2.2. Accomplishments of the 1993 Five-Year DIII–D Plan and Context for the 1998 Five-Year Plan .......................................................................................................3-6 3.2.3. DIII–D Scientific Progress and Accomplishments .................................................................3-12 3.2.4. DIII–D Operations and Facility Improvements.......................................................................3-17 3.2.5. Transition to a National Program ..........................................................................................3-20 LIST OF FIGURES 1-1.The DIII–D program plan progresses from short pulse AT physics, through optimization, to 10 s operation .................................................................................................................................1-3 1-2.DIII–D Advanced Tokamak research plan will integrate the upgraded heating and divertor to optimize performance ..........................................................................................................................1-5 1-3.Implementation of the proposed DIII–D research requires the plasma control tools defined in the facility upgrades ............................................................................................................1-7 1-4.Pursuit of the key research thrusts requires the diagnostic upgrades included in the DIII–D Plan ....................................................................................................................................1-7 1-5.Recent technical developments of 110 GHz gyrotrons and a high-power diamond window (upper right) motivate an accelerated ECH program ..........................................................................1-19 1-6.We plan to implement a high triangularity pumped divertor in stages .................................................1-20 1-7.The DIII–D upgrade plan includes contingency options to adapt to evolving scientific outcomes ..............................................................................................................................1-20 iv General Atomics Report GA-A22950 THEDIII–D FIVE-YEARPROGRAMPLAN1999–2003Project Staff 2.1-1.DIII–D Program linkages provide intellectual inputs, research inputs and staff opportunities .............2.1-3 2.1-2.The DIII–D research plan culminates in integrated, Advanced Tokamak operating scenarios ...........2.1-5 2.1-3.DIII–D program schedule ....................................................................................................................2.1-7 2.2-1.The 1999–2003 research plan advances facility capability in step with advancing confinement, stability, boundary and current drive science .................................................................2.2-4 2.2-2.ECH barrier control is illustrated by a three-case comparison ............................................................ 2.2-20 2.3-1.E ×B shear suppression enables transport barrier control....................................................................2.3-4 2.3-2.An opposing NB will enable transport barrier control through manipulation of E ×B shear .................2.3-7 2.3-3.DIII–D E ×B shear regulation occasionally results in modest electron transport reductions.................2.3-9 2.3-4.Energy confinement enhancement factor increases with pedestal pressure in ITER ......................... 2.3-15 2.3-5.Stability limits for the n=1 ideal kink mode .......................................................................................... 2.3-24 2.3-6.Wall stabilization is predicted to allow ideal n=1 kink stability.............................................................. 2.3-25 2.3-7.Simulations with good experimental foundation indicate additional particle pumping will maintain higher q(0) ....................................................................................................................... 2.3-29 2.3-8.Better bootstrap alignment could increase l i while preserving NCS ................................................... 2.3-31 2.3-9.Strong emissivity peaks at low temperatures is the key to a radiative divertor ................................... 2.3-36 2.3-10. The standard model predicts radiated heat flux limits for the divertor .................................................2.3-36 2.3-11. Radiation evenly distributed from the X–point region is in stark contrast to standard divertor model predictions ................................................................................................................... 2.3-38 2.3-12. T e measurements do not support model predictions of significant electron conduction ..................... 2.3-39 2.3-13. Divertor measurements and modeling show < 2 e V T d , permitting volume recombination to compete with ionization ................................................................................................................... 2.3-40 2.3-14. Volume recombination remains small until the momentum is reduced via ion-neutral interactions .......................................................................................................................................... 2.3-41 2.3-15. Carbon radiation dominates partially detached divertor operation induced by deuterium puffing ....... 2.3-42 2.3-16. Either impurities or better neutral baffling are needed to achieve the AT scenario .............................. 2.3-44 2.3-17. Slanted RDP structures should aid in obtaining impurity enrichment in the divertor............................ 2.3-45 2.3-18. Pellet fueling with divertor pumping shows the Greenwald limit is not an obstacle ............................ 2.3-52 2.3-19. Scientific progress: DIII–D fusion performance has doubled every 2 years ....................................... 2.3-53 2.3-20. A large pressure decrease in ELMing H–mode discharges is rewarded with an increase in confinement quality .......................................................................................................................... 2.3-54 2.3-21. Models predict the RDP baffles will reduce core ionization by an order of magnitude ........................ 2.3-55 2.3-22. A 26 MW energy loss per Type I ELM is predicted for ITER ................................................................ 2.3-57 2.3-23. Localized noninductive current drive can yield improved confinement and stability ........................... 2.3-64 2.3-24. The allowable power range of DIII–D AT scenarios can be estimated from simple relationships ....... 2.3-66 2.3-25. Optimum ramp-up begins at ß p close to the equilibrium limit .............................................................. 2.3-70 2.3-26. One–dimensional simulations show bootstrap overdrive can generate 1 MA in 2 s ........................... 2.3-72 2.4-1.DIII–D research connects to four possible tokamak program directions .............................................2.4-2 2.4-2.The major radius of superconducting tokamaks is constrained by wall loading at low aspect ratio and by stress at high aspect ratio ....................................................................................2.4-8 General Atomics Report GA-A22950v Project Staff THEDIII–D FIVE-YEARPROGRAMPLAN1999–2003 2.4-3.High aspect ratio superconducting tokamaks have relatively low fusion power ..................................2.4-8 2.4-4.DIII–D research projects to a spherical tokamak power system ......................................................... 2.4-16 2.5-1.The DIII–D tokamak facility spans a half city block .............................................................................2.5-2 2.5-2.The heart of the facility is the DIII–D tokamak with its many support systems, utilities and diagnostics ...................................................................................................................................2.5-3 2.5-3.DIII–D capabilities allow a wide range of research and technology issues to be addressed ..............2.5-5 2.5-4.The entire DIII–D first wall is graphite .................................................................................................2.5-5 2.5-5.The upper divertor cryopump is optimized to pump highly triangular double-null divertor discharges ..............................................................................................................................2.5-6 2.5-6.An extensive array of computer systems operates the tokamak and collects and analyzes the data ................................................................................................................................2.5-7 2.5-7.Quarterly boundary radiation levels show the site is maintained well below the 40 mrem operating limit ......................................................................................................................................2.5-9 2.5-8.Proposed facility development incorporates ideas from GA, collaborators and the February, 1998 workshop .................................................................................................................... 2.5-10 2.5-9.The carbon first wall and divertor targets protect the vacuum vessel and limit high-6 impurities ....... 2.5-16 2.5-10. The planned completion of the Radiative Divertor installation includes the lower baffle and the private flux baffles .................................................................................................................. 2.5-17 2.5-11. Divertor and first wall surface options will be tested on DIII–D ........................................................... 2.5-19 2.5-12. The toroidal field coil is capable of 10 s and longer pulse operation with the completion of the proposed upgrade ..................................................................................................................... 2.5-21 2.5-13. Additional coils would give an improved match to the outer vacuum vessel wall mode structure ...... 2.5-24 2.5-14. The new MSE system features a tangential and radial view of a single beam line ............................. 2.5-32 2.5-15. New interferometer concept overcomes the difficulty with measurement of the first order term ......... 2.5-36 2.5-16. Several possible beamline rotation options would allow counter-injection .......................................... 2.5-48 2.5-17. The LANL RACE compact toroidal injector is of the size needed for DIII–D ....................................... 2.5-51 2.5-18. Operation of DIII–D at 3.4 T requires upgrades .................................................................................. 2.5-52 2.6-1.The DIII–D program advances fusion energy science and improves the tokamak concept ...............2.6-2 2.6-2.DIII–D collaborates with the world’s premier tokamak facilities ..........................................................2.6-4 2.6-3.The DIII–D tokamak is capable of producing plasma shapes of other tokamaks ............................... 2.6-14 2.6-4.The DIII–D program is implemented through a line management organization which includes collaborators and four GA research divisions ....................................................................... 2.6-35 3-1.Scientific progress: DIII–D fusion performance has doubled every two years ...................................3-12 LIST OF TABLES 1-1.DIII–D program collaborators insure coordination of national and international tokamak optimization ..........................................................................................................................1-4 2.1-1.Advanced tokamak program — objectives, challenges, and targets ..................................................2.1-6 vi General Atomics Report GA-A22950 THEDIII–D FIVE-YEARPROGRAMPLAN1999–2003Project Staff 2.1-2.DIII–D program collaborators .............................................................................................................. 2.1-11 2.2-1.Program logic defines tools and approaches ......................................................................................2.2-5 2.2-2.Parameters of DIII–D scenarios .......................................................................................................... 2.2-18 2.3-1.Results of dimensionless parameter scaling experiments in DIII–D for various regimes .................... 2.3-11 2.3-2.Tools for L–H transition physics studies .............................................................................................. 2.3-14 2.3-3.Elements of divertor physics ............................................................................................................... 2.3-36 2.3-4.Enrichment of neon and argon is presented for four cases of induced deuterium flow ...................... 2.3-43 2.4-1. ρ * scaling from ITER to various tokamaks ..........................................................................................2.4-3 2.4-2.From ITER to DIII–D and Alcator C–Mod varying ν * and ρ * ...............................................................2.4-5 2.4-3.DIII–D contributions to ITER ................................................................................................................2.4-6 2.4-4. ρ * scaling from an optimized superconducting power plant to DIII–D ................................................ 2.4-10 2.4-5.DIII–D contributions to the superconducting tokamak path ................................................................. 2.4-12 2.4-6. ρ * scaling from DIII–D to a compact ignition experiment ..................................................................... 2.4-14 2.4-7.DIII–D contributions to the compact ignition path ................................................................................ 2.4-15 2.4-8. βscaling from an ST pilot plant to DIII–D ........................................................................................... 2.4-19 2.4-9.DIII–D contributions to the ST path ..................................................................................................... 2.4-20 2.4-10. DIII–D contributions to future tokamak paths ...................................................................................... 2.4-21 2.5-1.Power to plasma of auxiliary heating systems ....................................................................................2.5-6 2.5-2.Power capability of heating systems after pro posed upgrades are complete .................................... 2.5-11 2.5-3.Summary of the five areas of research into nonaxisymmetric magnetic phenomena and how they would be addressed by the proposed external and internal coil systems ............................ 2.5-23 2.5-4.Diagnostic systems installed on DIII–D ............................................................................................... 2.5-29 2.5-5.Upper divertor diagnostic additions ..................................................................................................... 2.5-30 2.5-6.Lower divertor diagnostic modifications .............................................................................................. 2.5-31 2.6-1.DIII–D program collaborators ..............................................................................................................2.6-1 2.6-2.Recent SBIR collaborations with the GA Fusion Group ......................................................................2.6-9 2.6-3.DIII–D 1997 experiments emphasized urgent ITER physics R&D ...................................................... 2.6-16 2.6-4.General Atomics provides ITER support in addition to DIII–D program support ................................. 2.6-17 2.6-5.Past and present graduate and post-doctoral students at DIII–D ....................................................... 2.6-19 2.6-6.DIII–D collaborations related to stability and disruption physics ......................................................... 2.6-21 2.6-7.DIII–D collaborations related to transport and fluctuations ................................................................. 2.6-22 2.6-8.Recent collaborations related to DIII–D work in the wave/particle topical area .................................. 2.6-23 2.6-9.DIII–D collaborations related to divertor and boundary physics ..........................................................2.6-24 2.6-10. Programmatic responsibilities of major DIII–D U.S. collaborators ...................................................... 2.6-25 2.6-11. Programmatic roles of DIII–D university collaborators (1997) ............................................................. 2.6-25 2.6-12. Programmatic roles of other collaborations ......................................................................................... 2.6-26 3-1.Changes in five-year plan since July 1997 ..........................................................................................3-1 3-2.Comparison of 1993 upgrade plan with actual upgrades implemented ..............................................3-7 3-3.An assessment of progress on the 1993 advanced tokamak research goals .....................................3-8 General Atomics Report GA-A22950vii Project Staff THEDIII–D FIVE-YEARPROGRAMPLAN1999–2003 3-4.An assessment of resolution of 1993 divertor research program functions/needs issues ..................3-10 3-5.An assessment of accomplishments of 1993 divertor program goals and guidelines .........................3-10 3-6.Integrated advanced tokamak parameter goals and achievements ....................................................3-11 3-7.Comparison of 1993 plan and actual GA funding levels and operations weeks .................................3-17 3-8.Facility improvements planned and implemented in FY94–98 ............................................................3-18 3-9.An assessment of the 1993 five-year DIII–D new diagnostic plan and accomplishments ..................3-19 3-10.New diagnostics implemented on DIII–D that were not anticipated in the 1993 five-year plan ...........3-20 viii General Atomics Report GA-A22950 THEDIII–D FIVE-YEARPROGRAMPLAN1999–2003Project Staff 1. THE DIII–D FIVE-YEAR PROGRAM SUMMARY 1.0.1. THE DIII–D NATIONAL PROGRAM OVERVIEW AND MISSION The strategy for the recently restructured U.S. Fusion Energy Sciences Program focuses on innovation and scientific discovery to strengthen the program’s ties to other fields of science, to position the United States to continue playing a meaningful role in the world fusion energy effort within available resources, and to preserve the basis for a future expanded U.S. Fusion Energy Program. The DIII–D Research Program is a cornerstone element in this national fusion program strategy (see 2.1). The problem addressed by this proposal is the optimization of the tokamak. Within this context, the DIII–D Program mission is: To establish the scientific basis for the optimization of the tokamak approach to fusion energy production. The DIII–D Program is an Advanced Tokamak (AT) Program using and advancing fusion energy science to provide the basis for future fusion initiatives. Tokamak optimization has been a basic organizing thrust of the DIII–D Research Program for several years. In implementing the new DIII–D research plan, we will pursue AT science and integrated performance optimization as the most promising direction for determining the tokamak’s highest potential. The DIII–D Program mission seeks to develop and exploit fusion science (confinement, stability, power and particle control, and current drive) to advance fusion energy. DIII–D will produce demonstrated, scalable plasma performance; backed up by a firm, comprehensive theoretical model; and achieved in a configuration that has the potential to be attractive as a power plant concept. Thus, the proposed research will contribute significantly to the three legs of the U.S. Fusion Program: fusion ener- gy science, concept innovation, and burning plasmas. In support of the DIII–D overall mission, the specific goals of DIII–D AT research in the period 1999–2003 are: l To attain the theoretically predicted minimum in the cross-field transport of heat and energy; l To extend the operation of DIII–D to the theoretically predicted limits of plasma stability; l To seek a plasma that exhibits full recombination in the divertor before it reaches a material sur- face, thus achieving the simple description of magnetic confinement as using magnetic fields to prevent hot plasma from touching a material surface; l To develop methods of plasma current generation (initiation, ramp-up, sustainment, and profile control) to provide future devices the basis for full steady-state transformerless operation; and General Atomics Report GA-A229501–1 Project Staff THEDIII–D FIVE-YEARPROGRAMPLAN1999–2003 l To integrate the above objectives in single steady-state operational scenarios to demonstrate the possibility of simultaneous optimization of the tokamak in the four major areas of fusion science. The DIII–D National Program consists of a tokamak facility with its operating staff and a national collaborative research team that utilizes the facility to carry out research to support the goals of the U.S. Fusion Energy Sciences Program. DIII–D is the world’s most flexible tokamak and the largest magnetic fusion device in the U.S. program. Its ability to control a variety of complex plasma shapes and its diagnos- tic instrument set are the best in the world. It has reliable heating and current drive systems, pumped diver- tor systems, and a digital plasma control system capable of achieving the plasma control essential to the tokamak optimization mission. The DIII–D open data system architecture enhances the effectiveness of the large collaborative national team. The DIII–D Program has strong linkages (Section 2.6) to foreign and domestic experiments (the U.S. Theory Program) enabling technology development programs, the general science community, and the designers of future fusion initiatives such as International Thermonuclear Experimental Reactor (ITER). Links to universities and laboratories provide broad intellectual input to the DIII–D Program and provide paths for flow of research results between other groups and the DIII–D Program. 1.0.2. THE PROPOSED DIII–D FIVE-YEAR PROGRAM PLAN An outline of the proposed research plan is presented in Fig. 1–1. Two major in-vessel installations divide the upcoming five-year time frame into three major experimental periods. The research emphasis progresses from short pulse AT physics to extended pulse and more optimized AT physics, and then to sustained 10 second AT physics. During the fall of 1999, we expect to complete the private flux baffle and pump in the upper divertor of the DIII–D vessel. In year 2000, we expect to com- plete installation of a set of external asymmetric magnetohydrodynamic (MHD) feedback coils. During the fall of 2001, we expect to complete installation of the lower divertor upgrade. By adding 110 GHz microwave gyrotrons, the ECH power will reach 6 MW in the fall of 2000 and 10 MW by 2003. These installations naturally separate the experimental program into three parts: l The first period will continue the present research program into 1999. We expect to obtain deeper understanding of transport, obtain results on the improvement of stability limits using wall stabi- lization, elucidate the mechanisms which lead to edge instabilities that limit high confinement regimes and reduce the maximum beta, exploit the microwave heating and current drive, increase understanding of the physics of parallel heat transport in the scrapeoff layer and divertor, and fur- ther explore plasma shape optimization. l The period 1999–2001 will be an intensive AT experimental period devoted to exploring the open-versus-closed divertor question and to developing pressure and current profile control and fueling techniques for sustained, quasi-stationary operation. Further experiments to implement theoretically predicted optimized profiles will also be undertaken. 1–2General Atomics Report GA-A22950 THEDIII–D FIVE-YEARPROGRAMPLAN1999–2003Project Staff l The third intensive experimental period, from the end of 2002 through 2003, will be devoted to using the systems installed in 2001 to develop integrated, near steady-state (10 s), optimized AT scenarios. There will be a particularly intensive effort to control the current profile and the pres- sure profile using rf systems using the full double-null divertor. 1.0.3. LEADERSHIP A key responsibility of the DIII–D Program, for the period 1999–2003, is to provide national program leadership in optimization of the tokamak approach to fusion energy. We propose to accomplish this mis- sion with the diverse capabilities of the DIII–D National Team consisting of about 120 operating staff and 100 research scientists drawn from 8 U.S. National Laboratories, 19 foreign laboratories, 17 universities, and 5 industrial partnerships (see Table 1–1 and Section 2.6). As the contractor for the DIII–D National Fusion Facility, GA will provide leadership for the DIII–D Program of toroidal fusion research. GA is responsible for optimizing the pace for the research program for the most scientific and cost-effective output, and for safe and environmentally sound operation in accordance with applicable DOE, federal, state, and local government rules and regulations. General Atomics Report GA-A229501–3 Project Staff THEDIII–D FIVE-YEARPROGRAMPLAN1999–2003 Activity/ Calendar Year Operation (weeks) Facility upgrades ECH2 MW Asymmetric MHD feedback coils10 s pulse 3 MW6 MW Upper Lower 10 MW Divertor Tokamak Operation Schedule Research program New diagnostics ITER physics R&D and pulsed AT physics • Central Thomson • Divertor diagnostics • 35 Chan MSE • Divertor flow • Electron transport • 3–D Equlibrium Optimize and extend ATIntegrate and sustain AT 14111818181818 1997199819992000 5-year contract period 200120022003 RUN RUNRUN RUN Fig. 1–1. The DIII–D program plan progresses from short pulse Advanced Tokamak physics, through optimization, to 10 s operation. The baseline plan is to operate 18 weeks per year for each of the next five years. The electron cyclotron heating capacity will increase to 6 MW by 2001 and 10 MW by 2003 and installation of the upper and lower radiative divertors are scheduled for 1999 and 2001. TABLE1–1 DIII–D PROGRAMCOLLABORATORSINSURECOORDINATION OF NATIONAL ANDINTERNATIONALTOKAMAKOPTIMIZATION National International Laboratories Universities Laboratories ANLCal Tech ASIPP (China) INELColumbia U.Cadarache (France) LANLHampton U.CCFM (Canada) LLNL*Johns Hopkins U.Culham (England) ORNL*Lehigh FOM (Netherlands) PNLMITFrascati (Italy) PPPL*Moscow State U.Ioffe (Russia) SNL*Palomar College IPP (Germany) RPIJAERI (Japan) U. Maryland JET (EC) Industry Collabs U. Texas KAIST (Korea) Comp XU. Washington Keldysh Inst. (Russia) CPI (Varian)U. Wisconsin KFA (Germany) GA*UCBKurchatov (Russia) Gycom UCILausanne (Switzerland) Orincon UCLA*NIFS (Japan) UCSD*Troitsk (Russia) SWIP (China) Tsukuba U. (Japan) *DIII–D Executive Committee Membership. General Atomics’ leadership responsibilities include maintaining: •ADIII–D Executive Committee, including GA and collaborator members to advise the director on program planning, direction, priorities, and budgets. •ADIII–D Program Advisory Committeecomposed of technical experts from other laboratories to provide outside peer review. •ADIII–D Long-Range Planto chart DIII–D Program goals and milestones coordinated with major DIII–D collaborators. •ADIII–D Research Planto detail planned activities for at least a one-year period. 1–4General Atomics Report GA-A22950 THEDIII–D FIVE-YEARPROGRAMPLAN1999–2003Project Staff 1.1. TOKAMAK RESEARCH USING THE DIII–D NATIONAL FACILITY (SOW AND WBS TASK 1) The technical approach which we will use to pursue the DIII–D Program mission and goals can use- fully be described in different cross-cutting ways. At the highest level, we see the Program as two main lines, core plasma and boundary plasma physics, both of which work toward an eventual integration demonstrated by sustaining a 5% beta plasma for 10 seconds. Figure 1–2 of this volume gives some of our numerical targets for tokamak optimization and indicates some of the areas of integrated research between core and boundary physics. The second way we view the program is as an integrated AT Program (see Section 2.2). The AT Program approach to optimizing the tokamak is expressed in lines of action or research thrusts. Our abili- ty to pursue these research thrusts motivates the plasma control tools and diagnostics the program needs. Finally, the broadest view of the DIII–D Program is by the science topical areas (confinement, stability, power and particle control, and steady state). We present the program in those WBS categories. General Atomics Report GA-A229501–5 Project Staff THEDIII–D FIVE-YEARPROGRAMPLAN1999–2003 CY98992000 CORE PHYSICS BOUNDARY PHYSICS 010203 10 MW ECH6 MW ECH RADIATIVE DIVERTOR DIVERTOR OPTIMIZATIONS • REACH MAXIMUM STABILITY LIMIT • ATTAIN NEOCLASSICAL CONFINEMENT • ACHIEVE 100% BOOTSTRAP CURRENT • ATTAIN PARTICLE CONTROL WITH DOUBLE NULL DIVERTOR • OPTIMIZE EDGE CONFINEMENT AND STABILITY • ACHIEVE RECOMBINING DIVERTOR PLASMAS INTEGRATED ADVANCED TOKAMAK PHYSICS • STABILITY β N = 6, CONFINEMENT H = 4 • 100% BOOTSTRAP CURRENT • 100% RECOMBINATION • HIGH PLASMA PRESSURE PHYSICS OF H–MODE INTERFACE LAYER • HIGH TEMPERATURE • LOW NEUTRALS • HIGH CURRENT DRIVE EFFICIENCY • STRONG PUMPING OF OPTIMAL SHAPE • HIGH RADIATION LONG PULSE • HIGH DIVERTOR POWER HANDLING Fig. 1–2. DIII–D Advanced Tokamak research plan will integrate the upgraded heating and divertor to optimize perfor- mance. Core plasma physics and boundary physics studies will culminate in 10 second, 5% beta operations. RESEARCH THRUSTS The four principal DIII–D research thrusts are: 1. Controlling interior plasma profiles and wall stabilization for higher stability and confinement. 2. Controlling the plasma edge for sustained AT performance and better confinement. 3. Developing the basis of steady-state operation. 4. Developing advanced divertor operating modes. Figures 1–3 and 1–4 of this section show diagrammatically the required plasma control tools and diag- nostic upgraded needed to pursue the DIII–D Research Program. Detailed descriptions of these upgrades and enhancements to DIII–D are given in Section 2.5. The research thrusts are described in