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GA-C19462DIII-D EXPERIMENTAL PLANFOR FY-1989bYFUSION DIVISION STAFFJ.L. LUXON, EDITORPreparedContract No.for the SanNOVEMBER 1988AGENEHL ATOMICS
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GA-C19462DIII-D EXPERIMENTAL PLANFOR FY-1989bYFUSION DIVISION STAFFJ.L. LUXON, EDITORPrepared underContract No. DE-AC03-89ER51114for the San Francisco Operations OfficeU.S. Department of EnergyGENERAL ATOMICS PROJECT 3466NOVEMBER 1988
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APPROVALSApproved:PILVJ(&\T.C. S’unonenDIII-D Program DirectorFusion DivisionGeneral AtomicswDateDatee Project MDOEISANErol OktayIDIII-D Program ManagerDivision of Confinement SystemsDOE/ER-55.mDateI
This document presents the planned experimental activities for the DIII-D toka-mak facility for the period FY 1989. This plan is part of a five year contract betweenGeneral Atomics and the Department of Energy. The plan will be reviewed by both organizations and approved by the DIII-D Program Director, Fusion Division, GeneralAtomics, the Onsite Project Manager, S A N Office, DOE, and the DIII-D ProgramManager, Division of Confinement Systems, Washington,D.C.It is anticipated that this document will be updated yearly, and that the progressof the DIII-D program will be reviewed quarterly against this plan. In the event ofmajor budgetary, technical, or programmatic changes this document will be revised.iv
LIST OF ACRONYMSAPSAmerican Physical SocietyaMinor radius of plasmaBMagnetic fieldCITCompact Ignition TokamakDIII-DTokamak Fusion Device located at General AtomicsECHElectron Cyclotron HeatingELMEdge localized mode that limits energy storage in plasmaFYFiscal yearH-modeA high regime of tokamak confinementIPlasma currentIAEAInternational Atomic Energy AgencyIBWIon Bernstein Wave method of ion cyclotron heatingITERInternational Thermonuclear Experimental ReactorJETJoint European Tokamak located in EnglandL-H %ansitionTransition fiom L-mode to H-modeL-modeA low regime of tokamak confinementNBINeutral beam injectionOFEOffice of Fusion EnergyV'
c'!ic!0-modeA mode of microwave propagation in which the microwaveelectric field is pardel to the toroidalmagnetic fieldqTokamak safety factor q 3 meam that a magneticfield line traverses the toroidal direction threetimes in one poloidal rotation.R.&DResearch and developmentrfRadio frequencyX-modeA mode of microwave propagation in which the microwaveelectric field is perpendicular to the toroidalmagnetic fieldx-pointThe location where the magnetic field is purelytoroidal (no poloidal component). ,PThe ratio of plasma pressure to magnetic field pressure.nZHHydrogen ion cyclotron frequency.vi
r;!\L'CONTENT.111FOREWORD. . . . . . . . . . . . . . . . . . . . . . . .ivLIST OF ACRONYMS . . . . . . . . . . . . . . . . . . . . .v1. INTRODUCTION . . . . . . . . . . . . . . . . . . . . .12. SUMMARY . . . . . . . . . . . . . . . . . . . . . . . .33. EXPERIMENTALPLAN . . . . . . . . . . . . . . . . . . . 84. GOALS FOR EXPERIMENTS IN 1989 . . . . . . . . . . . . 105. DETAILED RESEARCH PLAN . . . . . . . . . . . . . . . . 136. DETAIL HARDWARE PLAN . . . . . . . . . . . . . . . . . 157. MILESTONE SCHEDULE (Research Operations) . . . . . . . . 17APPROVALSvii
c';1. INTRODUCTIONThis document summarizes the Experimental Plan for the DIII-D tokamakfacility for the fiscal year 1989. The long-range DIII-D 5 yr plan is directed ultimately at the goal of achieving good confinement at high beta in a plasma withnon-inductively driven current. This is important to the design of a steady-statereactor. This program may be thought of as occurring in two phases. In the firstphase of the program we are separately investigating high beta plasma confinementin inductively-driven plasmas, and non-inductive current drive. In the second phasewe will combine these two elements to investigate high beta plasma confinement withnon-inductive current drive.The F Y 89 plan continues the first phase of the DIII-D experimental effort thatcontains a strong focus on beta and confinement in non-circular plasma configurationsand in the divertor configuration in particular. Important work also continues in thedevelopment of rf heating systems for heating, profile control, and current drive. Thisresearch is coupled to theoretical efforts at General Atomics.The FY 89 research program outlined herein is diverse and multifaceted. However, it is also characterized by a greater synthesis of techniques toward a commongoal. An example is the application of ECH for sawtooth suppression that wouldimprove the low Q confinement and allow higher p to be obtained. We believe thisresearch program will provide a solid foundation for the continued development of thetokamak toward high beta steady-state reactor application.The DIII-D FY 89 research program will provide results that will help resolvemany CIT and ITER Physics R&D issues. In addition, DIII-D confinement studieswill be an important input to the newly formed National Transport Task Force.1
The outline for the remainder of this plan is as follows:Sec. 2.S u m m a r y discussion of the Experimental Plan.3. A bar chart which summarizes the proposed Experimental Plan.4.A s u m m a r y of the research goals for FY 89.5.A tentative detail breakdown of the research plan.6.A detail plan for major hardware tasks.2
TLONG-RANGEIICYIFY86IINON INDUCTIVE CURRE TDRIVEBETA GOALS IPHYSICSHIGH BETA (I01IIPlasma ProductionIAchieve H-modeICONFINEMENT (01III1IDIVERTORIEDGE (IIIII1IIICH11CURRENT DRIVE (PHYSICS MILESTONESIIIIIIIIIIII.IIIIIIIIII.Heat LoadsIFY88IIIIIIIDensity Feedback.Neutral PressureCounter InjectionIElm/St Suppressionl Low qIIIStrike Point SweepIIOutside LaunchHeatingIElm/St ControlIH-ModeFW Coupling ta H-ModeConnectlod t o TheoryIIIIIIIIIIIIIIIIIIIIIIIIIIII"1IOhmic HmodeILansmuir ProbeIAdvanced ShapeProfile Control 1'Double NullkhapeITopologyI2.5MA Deuterium 01I1i -With IBWITopDIvertorInside WallWall ConditioningTangential H -alphaHeat LoadsEdge C Q Parti:1Ass/Xltslde LaunchInside LaunchiH-ModePro1 e ControlElm,dIII1IBW Heat 9Demonstrate N8CDHjProfile CorKDScallng!InsldeLaur!Non Indu!@ Eva1U.e Conflnement with NA Repofit on Oublde Launch ECIIIIIIIIIIIIIIIIIIII.IIH m o d e scalingCurrent scalingElm Physics .1OPTIMI;DEVELQ0 0.3MA d 112%betaHigh BetaBetaLimit4FY89DEVELOP HIGH BETA PLASMAS WITHINDUCTIVE CURRENT DRIVEBUILD ECH & ICH SYSTEMSINITIALOPERATIONRESEARCH OBJECTIVESIFY87Report on Divertor ! dies .IReportonBetaF ults0 ReportonC ble NullRI irt on beta llmlt ,O A !ss Confinement'Compare Inside/'Assess ECH ProAssess NBCD0 Evaluate EI'Report or0 Report0 Ri0f0i:
XBLE Ii RESEARCH PLANIE! BETA WITH INDUCTIVE CURRENT DRIVEP NONINDUCTIVE CURRENT DRIVE METHODSIIIIiIerationEdge OptimizationICurrent Drive EffectsIIIIJmization[le ControlIht High Betak ControlIpodeIIIIIIII ECH withIFWCDI Power FWCDModestIStartupI1IIptside ECHIIIIIpIIIIIIIIIIIIIIIIIIIII(IIICurrent DriveProfile. IIIIII .IIIIIIIIII Two FreqECHI 6MW ECH. 3.6MW ECHI. I H-Mode 8 Scaling I4.5I 3.6MW1I0 Report IFWCD ResultsINd ICHModerate Power( FLI ECH)I-III(ECH FW)IIIIIIIIIIIIIIII Os Pulse11IIIIIIII0 ,Report Pellet ResuiisAssess Beta Studieb w i t h full CDInReport inital 1 15 GHz0 Aisess Confinement with RF ProfileIlb Report on Divertdr improvementI0 Report CD Peqformance w i t h BMWl RFHigh Beta for 5 SecII 0 Assess Confirkment I1 O M w ECHHigh PowerIIIIIII os PuiskIILIIIECH P o k e r ScalingIFW P o y e r Scaling 33 MVIIIIIIIOptimize B & c1 9 M W FWCDIIIIIIIIIIIIf o r 10secIIICD Proflie Effects0 Reporh Profile Control o f ilnlitsblAssess Edge Optimlzationv Report Initial F k ICH ResultsFCDbata Shape Dependencqhau Scaling t o 2.5MA in D[port Maximum beta x tauReport Combined N V D & ECCDIOptimizeIIICurrent DriveIIw. . .J.- . . .v tvaiuaceIDW voLenuaiI11F b HeatingF V H-ModeI!lenoderateIIIprolIIHighI.Pellet FuelingTransportIECCDjtlve10 2MA 0 5%III10'0Mode&Current DriveP r o f i b ControlIOPERATIONIO S H A 0 1%betIMA 0 2%IIlodeLONG PULSEDEVELOP HIGHER BETA AND HIGHER. NONINDUCTIVE CURRENT TOKAMAKII1IIIIIIIIIIIIIIIIIIIIIIIIIIIIIIII-
1989 will also contain initial efforts at affecting p limits using profile control from ECHor IBW. We also intend to try to reach higher numerical values of @T by pushing upto the p limit in the regime q 3. At present, the achieved p in this regime has beenlimited by the energy confinement time becoming independent of Ip for q 3. Wefeel this loss of current scaling at q 3 is owing to the combined action of sawteethand ELMS. Consequently, the research topics on sawtooth suppression and ELMsuppression appear variously under the beta, Confinement, and rf program headings.The effort to attain higher pT will also be helped by the neutron shielding whichwill enable deuterium neutral beam injection into deuterium plasmas which yieldshigher beam power and better plasma confinement. These advantages may be crucialto achieving high beta in some of the more advanced limiter plasma shapes whereH-mode is probably not available. In FY 89, we also intend to mount an experimentaimed at pushing into the second stable regime.Confinement ResearchThe confinement research program in FY 89 has components that relate to thebeta program, to producing scaling information for future machine design, and toproviding basic understanding in several areas of plasma transport research. H-modestudies will continue to be emphasized. The neutron shielding will allow us to obtainthe clear scaling information with deuterium neutral beam injection into deuteriumplasmas, uncomplicated by isotope effects. These data will also be our contribution toa joint effort with JET to extract the size scaling of H-mode from direct comparisonsof corresponding discharges in our two machines. Following up our first production ofH-mode with ECH alone and even with ohmic power alone, we will continue exploringrfproduced H-mode with ECH and IBW.In more basic studies, we will seek a greater depth of understanding of interior plasma transport coefficients and processes using pulse modulation techniquesand the UCLA scattering system. Because of our excellent rotation speed profilemeasurements derived from the charge exchange recombination diagnostic system,momentum confinement studies will come along as a by-product of scaling studies.5
Edge and Divertor ResearchBoundary physics studies in FY 89 will concentrate on H-mode topics and otherdivertor issues relevant to future machine design efforts. We perceive that the demonstration of long pulse, steady H-mode is a critical issue in future machine designs.We have already obtained a 4.4 second steady H-mode with good confinement char-acterized by grassy ELMs. We have also seen effective prevention of central impurityaccumulation by ELMs in high current operation. These lines of research on longpulse and impurity control will be continued. We will also study particle transport.An effort is underway to form a collaborative arrangement with other edge plasmaspecialists to provide the necessary studies of erosion/redeposition, main plasma exhaust, pumping and recycling, and helium exhaust. In this area, we note the criticalrole that the development of helium glow wall conditioning has played in our programthis year. Work will continue on defining effective methods of divertor plasma-wall interaction for future machine designs. In FY 87 and early 88, our detailed investigationof ELMS in H-mode led us to propose that ELMs are triggered by edge ballooninginstabilities. In FY 89, we will concentrate on the physics of the L-H transition,bringing to bear data from the UCLA scattering system and microwave reflectometersystem.Radiofrequency HeatingThe rf heating program will have two operational components in FY 89: electroncyclotron heating (ECH) and ion Bernstein wave heating (Il3W). The ECH programin FY 87 and 88 utilized second harmonic outside launch and studied heating, obtained H-mode, suppressed sawteeth, and suppressed ELMs. Because of the low cutoffdensity for the available outside launch X-mode waves,5 2 x 1013 cme3, this impressive list of accomplishments was performed in a density regime somewhat disjointfrom other experiments, especially the high beta work which is usually done at higherdensity. Because of our desire to use ECH for sawtooth and ELM suppression to improve confinement at low q in the beta program, we have installed both an X-modeinside launch ECH system for which the cutoff density is about 7 x 1013 cm-3 and an.0-mode outside launch system for which the cutoff density is 5 3 x 1013 m - Initial experiments with the inside launch system resulted in some damaged waveguideswhich we plan to repair during a torus vent this winter. The outside lairnch system is6
operational. In low density plasmas, ECH will assist NBI current drive by boostingthe electron temperature.The IBW research program will begin in FY 89. The entire antenna and 2 MWgenerator system is installed and being commissioned. We already know that Il3Wcoupling to H-mode plasmas is less sensitive to edge conditions than fast wave cou-pling. Initial experiments will concentrate on basic IBW heating mechanisms. Keyphysics issues are linear versus non-linear absorption mechanisms and majority versus minority heating schemes. By employing the tunability of the system, varyingthe toroidal field, and using different harmonic resonances, great flexibility in heatinglocation can be obtained. In particular, the IBW should be useful in pressure profilecontrol in low BT, high beta plasmas. This application takes on added importancesince we believe the modes which prevent the attainment of the highest value of pNaxe primarily pressure driven.Current Drive ResearchThe current drive program in FY 89 will continue to investigate neutral beam(NBI) current drive, make a preliminary assessment of ECH current drive, and studyneutral beam current drive combined with ECH. Initial NBI current drive experimentshave, in addition to driving substantial currents, shown that the second stabilityregime can be approached. This occurs by virtue of the relatively high plasma energydeveloped at modest current resulting in high pp. Further experiments are planned toexplore the second stable regime behavior. The ability of ECH to assist NBI currentdrive by increasing the electron temperature will be studied. Current drive using ECHalone may require reorienting either the inside or outside launchers. This changerequires hardware modifications and a vent, and it is currently being considered.7
3. EXPERIMENTAL PLANTable I1 stlmmarizes the overall program for the next year for the basic programelements. The plan consists of 22 weeks of operation. Two machine vents in Decemberand April are anticipated for ECH waveguide modifications, diagnostic improvements,and general maintenance. At the present time the most variable element is the timingof the ECH waveguide modifications. The key hardware completion dates are given toindicate significant changes in capability. The numbers indicate OFE DOE milestones.8
TABLE I IDIII-D FY 1989 RESEARCH PLANEXPERINEKERUN DAYSI10, IAEA, 1-4HEETINGS,tlP51-110ITORUS VENTSHARDWARE AVAIL&3ILITYSHIELDIMGECH, OUTSIDE LAUNCH 0-HDDEECH, INSIDE LbUNCH X-HODEIBN SYSTEHOPERATIOH ISSUESSHAPE COIITROLHI6H CURRENT DEVELOPHENTPULSE LENGTH EXTENSION!1iH16H BETA STUDIES- - -- , .
IPLASMA SHAPETRANSPORT STUDYIBH PROFILE CONTROLECH ELM SUPPRESSIONSECOND STABILITYCONFINEMENT STUDIESSCALING STUDIESSIZE SCALING OF H-MODE (JET1H-MODE WITH RF; (-STABILIZATION OF INSTABILITIESMODULATED TRANSPORTBOUNDARY PHYSICS STUDIESLON6 PULSE H-MODEWALL CONDITIONING ASSESSMENTRF HEATING (BASIC)ECH, OUTSIDE LAUNCH 0-MODEECH, INSIDE LAUNCH X-MODEIBU STUDIES (BASIC)CURREHT DRIVE STUDIES,,tI
.-4. GOALS FOR EXPERIMENTS IN 1989This section contains a short summary of the principal goals for the experimentson DIII-D during 1989. The work is broken down into five subject areas: beta studies,confinement investigations, boundary physics, rf heating program, and current drivestudies. Each of these areas supports the others; accordingly, in some cases, you willfind the same goal listed under two topics. The aim of most DIII-D experiments is tointegrate these individual topics. A common example is confinement studies carriedout at high beta with divertor discharges.4.1.BETA STUDIESThe main goals in the high beta area are:1.Develop effective control methods for more advanced plasma shapes includinga.Double-null divertorsb.Plasmas with elongation up to 3c.Plasmas with high triangularity and indentation.2.Extend the beta limit studies to these more advanced plasma shapes.3.Reach the p limit in the regime q 3.4. Explore the utility of profile control derived from ECH or IBW.5.Continue second stability investigations in high poloidal beta plasmas.6. Study plasma transport, including fast ion transport, at high beta.4.2.CONFINEMENT INVESTIGATIONS1. Study confinement with deuterium injection into deuterium plasmas up toplasma currents of at least 2.5 MA.10
2.Study H-mode produced with rf power alone (ECH and/or IBW).3.Improve confinement at lowQby stabilizing sawteeth and/or ELMS.4. Provide information on the size scaling of H-mode (jointly with JET).5.Perform a detailed transport study using pulse modulation techniques andscattering diagnostics.6.Study momentum confinement.4.3. BOUNDARY PHYSICS STUDIES1. Demonstrate and study long pulse (-5 sec) quasi-stationary H-mode plasmas. Study impurity transport properties.Study particle transport in H-mode to understand the flat to hollow density2.profiles and steep edge gradients.3.In general, understand the physics of the L-H transition. Identify the natureof the turbulence and fluctuations that correlate with L- versus H-mode.4. Document divertor region heat loads, particle loads, and impurity effects asa function of X-point position and for single- and double-null divertors.5.Continue to develop improved methods of wall conditioning.RF HEATING PROGRAM4.4.Both electron cyclotron heating (ECH) and ion Bernstein wave heating (IBW)will be studied.4.4.1.ECH Program1. Verify ECH fundamental mode heating physics.2.Attempt to produce and study H-mode with ECH alone.3.Enhance H-mode by means of central ECH to peak up profiles or edge ECHfor ELM stabilization.4. Stabilize sawteeth.11
(35.Assist NBI current drive.6. Provide a preliminary test of ECH current drive.4.4.2.IBW Program1. Explore and document IBW heating efficiency and coupling in various regimes.Key issues are linear versus non-linear heating mechanisms and majorityversus minority species heating regimes.2.Attempt to produce H-mode with IBW alone or in combination with ECH.3.Utilize IBW for pressure profile control in the high beta studies.4.5. CURRENT DRIVE STUDIES1. Assess (preliminary) ECH current drive.2.Assist NBI current drive with ECH.3.Investigate second stability behavior in current drive plasmas.12
5. DETAIL RESEARCH PLANTable I11
Electron Cyclotron Heating Edge localized mode that limits energy storage in plasma Fiscal year A high regime of tokamak confinement Plasma current ' International Atomic Energy Agency Ion Bernstein Wave method of ion cyclotron heating International Thermonuclear Experi
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