在tcv托卡马克中用中性束加热的一般性研究外文翻译.docx

上传人:b****5 文档编号:28746932 上传时间:2023-07-19 格式:DOCX 页数:15 大小:626.43KB
下载 相关 举报
在tcv托卡马克中用中性束加热的一般性研究外文翻译.docx_第1页
第1页 / 共15页
在tcv托卡马克中用中性束加热的一般性研究外文翻译.docx_第2页
第2页 / 共15页
在tcv托卡马克中用中性束加热的一般性研究外文翻译.docx_第3页
第3页 / 共15页
在tcv托卡马克中用中性束加热的一般性研究外文翻译.docx_第4页
第4页 / 共15页
在tcv托卡马克中用中性束加热的一般性研究外文翻译.docx_第5页
第5页 / 共15页
点击查看更多>>
下载资源
资源描述

在tcv托卡马克中用中性束加热的一般性研究外文翻译.docx

《在tcv托卡马克中用中性束加热的一般性研究外文翻译.docx》由会员分享,可在线阅读,更多相关《在tcv托卡马克中用中性束加热的一般性研究外文翻译.docx(15页珍藏版)》请在冰豆网上搜索。

在tcv托卡马克中用中性束加热的一般性研究外文翻译.docx

在tcv托卡马克中用中性束加热的一般性研究外文翻译

英文原文

AscopingstudyoftheapplicationofneutralbeamheatingontheTCVtokamak

AlexanderN.Karpushova,∗,BasilP.Duvala,RenéChavana,EmilianoFableb,Jean-MichelMayora,OlivierSautera,HenriWeisena

aEcolePolytechniqueFédéraledeLausanne(EPFL),CentredeRecherchesenPhysiquedesPlasmas,AssociationEuratom-ConfédérationSuisse,

CH-1015Lausanne,Switzerland

bMax-Planck-InstitutfürPlasmaphysik,Euratom-IPPAssociation,Boltzmannstra遝2,D-85748Garching,Germany

Articleinfo

Articlehistory:

Availableonline17March2011

Keywords:

TCVtokamakNeutralbeamheating

Abstract

TheTCVtokamakcontributestothephysicsunderstandingoffusionplasmas,broadeningtheparameterrangeofreactorrelevantregimes,byinvestigationsbasedonanextensiveuseoftheexistingmainexperimentaltools:

flexibleshapingandhighpowerrealtime-controllableelectroncyclotronheating(ECH)andcurrentdrive(ECCD)systems.AproposedimplementationofdirectionheatingontheTCVbytheinstallationofaneutralbeaminjection(NBI)withatotalpowerofwouldpermitanextensionoftheaccessiblerangeofiontoelectrontemperatures()towellbeyondunity,dependingontheNBI/ECHmixandtheplasmadensity.ANBIsystemwouldprovideTCVwithatoolforplasmastudyatreactorrelevantratios∼1andininvestigatingfastionandMHDphysicstogetherwiththeeffectsofplasmarotationandhighplasmaˇscenarios.ThefeasibilitystudiesforaNBIheatingonTCVpresentedinthispaperwereundertakentoconstructaspecificationfortheneutralbeaminjectorstogetherwithanexperimentalgeometryforpossibleoperationalscenarios.

1.Introduction

TCVisacompact(majorradius,minorradius,toroidalmagneticfield,plasmacurrentof),highelongated(vesselelongation3)toroidalfusionexperimentalmachine.Highpower,real-timecontrollable,injectionofwavesatthesecond(X2,3MW)andthird(X3,1.5MW)harmonicsofelectroncyclotronfrequencyconstitutetheprimarymethodofheating(ECH)anddrivingnon-inductivecurrent(ECCD)intheplasmawithelectrondensities,electrontemperatures,iontemperatures.TheflexibleplasmashapingandpowerfulECHsystemareusedtocontributeinmanyareasoftokamakresearch[1].

HighpowerX2-ECH,forrelativelylowdensityTCVplasmas,doesnotallowoperationatreactorrelevantratiosofiontoelectrontemperatures,astheelectron-ionclassicalCoulombcollisionthermalequilibrationtimeissignificantlylongerthanthecharacteristicconfinementtimes.ImplementationofdirectionheatingattheMWpowerlevelwouldallowtheextensionoftobeyondunityandfillthegapbetweenpresentpredominantlyelectronheatedexperimentsandfusionreactor[2].Theiontoelectrontemperatureratioisofparticularinterestintheprojectionofthetransportmechanismsfromexistingexperimentstoburningplasma.Theratioplaysakeyroleinthetransitionbetweeniontemperaturegradient(ITG)andtrappedelectron(TEM)modedominatedturbulentenergytransportmechanisms.IncreasingreducestheionandelectronenergytransportasobservedinDIII-DH-modeexperiments[3].NBIheatingmaythereforeallowTCVplasmastoreachhigherˇvalues,closetotheideallimitorbeyondathighelongation.

Injectionoffastatombeams(NBI)intotokamakisapossibleandwellusedmethodofauxiliaryheating.Followingionizationandcharge-exchange,fastatomsofthebeamaretrappedasplasmaionsandtransportenergyandmomentummainlytobulkionsifthefastionenergyisbelowcriticalenergy(Ecrit∼20forhydrogenbeamanddeuteriumplasma,)[4].TheproposedNBIsystemwouldthusalsoprovideTCVwithatooltoinvestigatefastionandrelatedMHDphysics[5]aswellasplasmarotationcontrol[6]forwhichTCVisalreadywelldiagnosed.ThebehaviouroftoroidalrotationinthevicinityofanITBisofparticularinterestbecauseofitsinfluenceontriggeringand/orsustainingthebarrier.TargetplasmascouldincludeITER-likeH-modeshapestogetherwithadvancedshapes,recentlyaccessibleonlyinohmicregimes【7】。

2.ScenariosofNBIheatingexperiments

ExperimentalscenariosfortheNBIexperimentsontheTCVarestronglylinkedtolimitationsimposedbyECHandECCD.FortheeITBsandfullynon-inductivescenariosonTCV,theaccessibleplasmadensityislimitedbytheX2cut-offincurrentdriveandelectronheatingexperiments.Conversely,efficientX3depositionisobtainedforelectrondensityintherangeofand

TheASTRAcode[8]wasusedtosimulatetheplasmaresponsetoneutralbeamheatinginthegeometryoftheTCVtokamak.ThecodesolvesequationsforelectronandiontemperatureandplasmacurrentdensitywiththeprescribedelectrondensityprofileandtotalplasmacurrenttakenfromTCVexperiment.Theuseoftheneoclassicalionheatconductivity[9]givesthatismatchedtotheCXRS[10]measurement.Theexperimentalelectronheatconductivitywasnormalisedtoobtaintheenergyconfinementtimepredictedbypowerlawscalings[11]:

IPB98(y,2)forELMyH-modeandstandardpowerlawregressionforL-mode.TheECpowerdepositionprofilewascalculatedbytheTORAYray-tracingcode.

2.1.HighdensityELMyH-moderegime

ThetargetparametersformodellingweretakenfromOhmicandX3heated(Table1,No.1.0)stationaryELMyH-modephasesofTCVdischarge[12].About95%ofinjecteddeuteriumNBpowercanbeabsorbedbytheplasmafortangentiallyinjectedbeam.Thesimulationsshowthatcanbeachievedwith∼0.8MWofNBIand1.3MWX3-ECH(Figs.1and2).Accesstoshouldbeattainableatincreased()NBorreducedX2-ECHpower.Thefastioncharge-exchange(CX)lossesonbackgroundneutralsstronglydependonthefirstwallrecyclingconditions,thedensityofbackgroundatoms,obtainedfromEIRENEmodelling,reducestheNBheatingefficiencyby∼15%(No.1.4),CXlossesonbeamneutralsareneglectable.

Athighplasmadensityandcurrent,neutralbeaminjectioncouldresultinanincreaseofthethermalfrom2.0(pure1.5MWX3-ECH)to2.6(2MWNBI),andcouldevenreachtheidealMHDlimit(∼3)resultingfromthefastparticlecontribution.Fastionslowingdowntimesinsuchregimesareoftheorderof,i.e.shorterorcomparablewiththebulkplasmaenergyconfinementtime,so,perturbationoftheionenergyMaxwelliandistributionbyfastionsisexpectedtobesmall(asinafusionreactor).

2.2.X2-ECandNBIheating

ModellingofNBheatinginlowdensityregimeswasperformedfor2MWX2-ECheatedL-modereferencedischarge(#31761,No.2.0).IncreaseoftheNBdepositedpowerperplasmaionatlowdensityresultsin∼2timeslower()thaninhighdensityregimeNBIpowerrequiredtoaccessof(scenarios2.1and2.2andFig.3).Near-normalNBinjectioncannotbeconsideredhereduetohighershine-throughlosses,resultinginfirstwalloverheatoftheTCVcentralcolumn.ASTRAsimulationsconfirmearlierexperimentalandnumericalstudiesoffastionorbitlossesontheTCV[13].Atlowplasmacurrent,fastionorbitlossesareextremelyimportantandbecomesubstantialforcounter-IpNBinjection(Fig.4);lossesincreaseathighionenergy(32%forD-NBand59%for,scenarios2.4and2.7)andforhigherNBatomicmass.

NBinjectionatlowplasmadensityandcurrentprovidesthepossibilitytostudythefastionandMHDphysics.Intheunfavourablescenario(like2.4),thedeliveredbytheNBpowerleadstothecreationofastrongfastionpopulationwithastoredenergyoffewtenskJthat,atlowcurrent,significantlycontributestotheidealMHDˇlimit.Fastparticleinstabilitieswoulddominatetheplasmabehaviourundertheseconditions[5].

3.Neutralbeamsinjectionlayout

TCVwasnotoriginallydesignedforneutralbeamheatingalthoughseveralrelativelywidemachinemidplanelateralportswereimplementedforgeneraldiagnosticflexibility.Thelocationofmagneticfieldcoils,forwhichmodificationisnotfeasible,andtheexistingsupportstructuresaremajorproblemsforNBIplasmaaccess,inparticularforthetangentialinjectiondirection.AccessforNBinjectorsthrough15cmdiameterports

withnearnormalinjection(tangencyradius)andthroughasingleØ10cmaperturenear-tangentialinjectionportwiththeaxispassingneartheinnerwallathasbeenanalysedin[13].Shinethroughforisworkableatthehighdensities;NBusageatlowdensitiesis,however,severelylimitedbyexcessiveshine-throughandhighinnerwallpowerloads.Themaximalacceptablepowerloadof7.6MW/fora1sdurationleadstotemperatureriseofgraphiteinnerwalltiles[14]of1000Kcorrespondingtoshine-throughofthe1MWbeamwiththe15cmfoot-printsize.

Amodelofaneutralbeamwithgeometricfocussingandangulardivergence[15]wasperformedtocalculatethebeamtransmissionandpowerloadonthecriticalscrapersintheNBIduct.Theacceptable∼80%beampowertransmittedintothetokamakfor1MW,,1sbeamwith200mA/cm2extractioncurrentfromtheionopticalsystemlocatedatabout250cmfromtheTCVportisfeasibleonlywithlowbeamdivergence:

0.7/0.8。

forØ10/15cmductaperturesrespectively.ThetransmissionofthehighpowerNBthroughnarrowportsdemandshighcurrentdensity,lowdivergenceneutralbeaminjectoronlyreachable,atpresent,bylowercurrentdiagnosticneutralbeams.ToallaytheserequirementsonbeamdivergenceandcurrentdensityamodificationTCVvacuumvesseltocreatenewport(s),specificallydesignedforNBHandfittedbetweenmagneticfieldcoils,isconsidered.TheavailablegapsbetweentoroidalandpoloidalmagneticfieldcoilsattheTCVmidplaneare22cminverticaland38cmintoroidaldirection.Thedesignofductwithinner

minimalapertureof20cm,wallthickness1cmand

展开阅读全文
相关资源
猜你喜欢
相关搜索

当前位置:首页 > 党团工作 > 党团建设

copyright@ 2008-2022 冰豆网网站版权所有

经营许可证编号:鄂ICP备2022015515号-1