edge-plasmas for act-1 improved models for radiating · 2016. 11. 25. · dt, tbm 2020 2030 2040...
TRANSCRIPT
FusionNuclearScienceFacility,Mo3va3onandtheProgramtoDevelopaBasisforPowerPlants
C.E.Kessel,PPPL
J.Blanchard,A.Davis,L.El-Geubaly,L.Garrison,N.Ghoniem,P.Humrickhouse,Y.Huang,Y.Katoh,A.Khodak,E.MarrioL,S.Malang,N.Morley,G.H.Neilson,J.Rapp,M.
Rensink,T.Rognlien,A.Rowcliffe,S.Smolentsev,L.Snead,M.Tillack,P.Titus,L.Waganer,G.Wallace,S.Wukitch,A.Ying,K.Young,andY.Zhai
4thIAEADEMOProgramWorkshop,Karlsruhe,Germany,November15-18,2016
This work was performed under the auspices of the U.S. Department of Energy by Lawrence Livermore National Security, LLC, Lawrence Livermore National Laboratory under Contract DE-AC52-07NA27344.
LLNL-PRES-612712
M.E. Rensink and T.D. Rognlien ARIES Project Meeting
San Diego, CA Jan. 22-23, 2013
Improved models for radiating edge-plasmas for ACT-1
1. Kinetic Monte Carlo neutrals for pumping 2. Multi-charge-state impurities for radiation
Required functionality and R&D for breeder blanket systemssystems
Presented by Neil Morley & Mohamed Abdou, UCLAWith contributions from the FNST community
Fusion Nuclear Science Pathways AssessmentGaithersburg, MD, December 3, 2010
1
FusionEnergySystemsStudies
TheFusionEnergySystemsStudiesTeamisExaminingtheFusionNuclearScienceFacility
WhatdoesanFNSFhavetoaccomplish?HowdowemeasuretheFNSFprogressforfusiondevelopment?HowdoestheFNSFaccomplishitsmission?Whatisthepre-requisiteR&DneededforanFNSF?WhatdoestheFNSFrequirefromourprogramtosucceed?HowdoesanFNSFfitinthelargerfusiondevelopmentprogram?Whatcri3calinsightsaboutthisfacilitycanbeuncovered,impactsofassump3ons,technicalchoicesandphilosophies,…?
TheFNSFistheFirstStepinaTwo-StepPathwaytoCommercialFusionPowerPlants
ITER FNSF DEMO PowerPlant
3dpa 37-74dpa 100-150dpa 150+dpaMaxneutrondamage
Maxplasmapulse
500-3000s 1-15days 15-365days 365+days
TBR ~0 ~1.0 1.05+ 1.05
Tblanket,Tcool,exit 285C,150C 550C,650C 550C,650C 550C,650C
Firststronglyburningplasma
DemonstraterouMnepowerplantoperaMons
Notechnicalgaps
316SS,CuCrZr,Be,W,H2O,SS304,SS430
MaterialsRAFM,PbLi,He,SiC-c,Borated-RAFM,W,baini3csteel
TheFNSFistheFirstStepinaTwo-StepPathwaytoCommercialFusionPowerPlants
FNSF DEMO
min
mod
max
ITER PowerPlant
Largelythesamestar3ngpointbasedonproposedfacili3es
TohavenotechnicalgapsfromDEMOtoaPP
Fusionnuclearbreak-in Rou3neelectricityproduc3on
AddiMonalR&DonDEMO
WhatisaPossibleTime-FrameandWhereDoestheFNSFReside*
DT,TBM
2020 2030 2040 2050
Non-DT,TBMITER
2060
DTHe/DDFNSFPresentandneartermconfinementdevices,shortpulseàtolongpulse
USDEMO
Pre-FNSFR&D ParallelFNSFR&Dandpre-DEMOR&D
Thisscheduleisusedforillustra3on
FNSFconstrucMon
FNSFdesignPre-CConcPrelimFinal
DEMOconstrucMon
Pre-CConcPrelimFinalDEMOdesign
*USdoesnotpresentlyhaveacommitmenttodesignandconstructtheFNSForDEMO
TheFNSFISNOTaPowerPlantBUT,itsprogramisdesignedtoestablishthe“database”forDEMOandsubsequentpowerplants…itcombinesresearch,development,anddemonstra3onsTheFNSFhasamul3-facetedpurposetobreak-intothefusionnuclearregime
1) Performthematerialsresearchwithinthenuclearfusionin-serviceenvironment
2) Establishtheopera3onoffusioncorecomponents(madeofthesematerials)overtheprototypicalrangeofenvironmentalparameters(T,pressure,hydrogen,etc.)withfusionneutrons
3) Establishtheopera3onofmul3plesubsystems/func3onscri3caltofusion,suchastri3umbreeding,recovery,control,fueling,exhaust,andstorage…..othersincludepowerhandling,maintenance,measurements,fusionenablingtechnologies,etc.
4) Establishtheultra-longplasmapulses,withhighperformance,sustainedbyarangeofplasmaenablingtechnologies
PowerPlantRelevanceiscri3caltotheFNSF,toprepareforfuturedevice’sopera3ngregimesandtoprovideacomprehensiveexperimentonthefusioncoreandex-core
Thepre-FNSFComponentDevelopmentandPhasedOpera3onontheFNSFareEssen3alforSuccess
Wewilluseahighlevelofpre-qualifica3onofmaterialsandcomponents
Wewilltestallmaterialsinthefusioncoreuptothean3cipateddpalevelbeforeopera3ngtothatdpalevelontheFNSF,withfissionandfusionrelevantneutronexposuresWewilltestthemostintegratedprototypepossibleofblanket,divertor,andlaunchercomponentsbeforeinstalla3on,inanon-nuclearintegratedfacility
OntheFNSF,thephasesrampuptheopera3ngparametersslowlytoprovidemonitoring
Theplasmadura3ons,dutycycles,dpa’s,andopera3ngtemperaturesareadvancedthroughthe1DD,and5DTprogramphasesInspec3onsandautopsyofcomponentsisusedtomonitorevolu3onofmaterials,requiringhighlyefficienthotcellturn-around,duringanygivenphaseandattheendofaphaseTestblanketmoduleswillbeusedfora“lookforward”,engineeringtes3ng,backupblanketconcepts,andmaterialsampletes3ng
OntheFNSFwewillhavesomefailures,butthepresenceofconstantfailuresareincompa3blewiththeplasma-vacuumsystemsandtheneedforradioac3vematerials
remotehandling
MissionsoftheFNSF,UsingMetricstoShowHowMuchProgressWeAreMakingtoAddressThem
Stronglyadvancefusionneutronexposureoffusioncore(ex-core)componentstowardpowerplantlevelsU3lizeandadvancepowerplantrelevantmaterialsOperateinpowerplantrelevantfusioncoreenvironment(T,p,v,B,etc.)Producetri3uminrequiredquan33es,compensa3ngconsump3on,decayandlossesExtract,process,inject,andexhausttri3uminmannerthatmeetsallsafetycriteria,andhighlevelofpredic3on,controlandaccountancyRou3nelyoperateverylongpulseplasmas,longerorlongenoughtoaccessrequiredphenomena,withsufficientplasmaperformanceAdvanceanddemonstrateenablingtechnologiesDemonstratesafeandenvironmentallyfriendlyplantopera3ons(tri3umleakage,hotcellopera3ons,radioac3vematerialhandling,etc.)Developpowerplantrelevantsubsystemsforrobustandhighefficiencyopera3onsAdvancetowardhighavailability,reliability,efficientmaintenanceopera3ons,etc.
SamplingofMetricsforSomeMissions ITER FNSF DEMO Power Plant
ARIES-ACT1/2 1. Strongly advance the fusion neutron exposure…..
Life of plant peak FW fluence, MW-yr/m2 (life of plant)
0.3 12.6 (8.4 FPY)
88 (40 FPY)
Peak FW fluence to replace blanket, MW-yr/m2 (dpa) (replacements)
0.3 (3) (0)
0.7, 1.9, 2.6, 3.7, 7.4 (7, 19, 27, 37, 74) (5)
15-20 (150-200) (4-6)
Peak FW neutron wall load, MW/m2 (average)
0.76 (0.56)
1.75 (1.18)
2.2 (1.46)
4. Produce tritium in quantities that….. TBR - total 1.06* 1.05 Tritium produced per year, kg
0.004 10.7 101-146
Li-6 enrichment 90% 40% OB FW hole/loss fraction
7-9% 4%
6. Routinely operate very long plasma durations…. Plasma on-time per year (ave)
5% 35% 85%
Plasma pulse duration, s
500-3000 1.2x106 2.7x107
Plasma duty cycle 25% 95% 100% βN H98 / q95 0.6 0.4 0.4-2.1 Q 5-10 4-6 25-48 fBS 0.25-0.5 0.52 0.77-0.91 Pcore,rad / (Palpha + Paux)
0.27 0.24 0.28-0.46
Pdiv,rad / PSOL 0.7 0.75-1.0 0.75-1.0 *depending on assumed H/CD systems
WhyPursueaSmallerFirstStep,liketheFNSF?Untestedregimeoffusionneutronsonmul3-materialsundermul3-factor
environment
Fissionexperiencewithmaterials(learnedfromPWRandbreederdevelopmentprograms)
- Extremesensi3vityofswellingwithtemperature- Impactsofirradia3ondoserateincreasedhardeningandthresholdforswelling- Impactsofsmallercons3tuents~0.5wt%canleadtoposi3veandnega3veeffects- Surfacecondi3ons,welds,andmetallurgicvariabilityprovidedwidevaria3onsin
irradia3onbehavior- Incuba3onperiodsthatdelaytheemergenceofaphenomena- Simultaneousmul3plevariablegradients(neutronfluence,temperature,stress)on
crackbehavior- Radia3oninducedsegrega3on,precipita3on,modifiedthermalprecipita3on- …....
Goalistoestablishtheactualfusionin-servicematerialandscien3fic/engineeringdatabaseonallcomponentsinthefusionneutronenvironmentandintheoverallenvironmentbeforemovingtolargersizeandelectricityproduc3onThisisNOTthesamedatabasethatweusedtopursuetheFNSF,itreplaces/augmentsit
Thesmallerintermediatestep(FNSF)onapathtopowerplantsàwhatcomesbeforeFNSF
Neutronirradia3onofindividualmaterialsin1)fusionrelevantneutronsource,2)fissionreactoranddoping,3)ionbombardmentTri3umscience(LiPb)Liquidmetalscience
Integratedblanketcomponenttes3ng&ITERTBMprogress(weaknuclear)
Prototypicalparameters&integra3on
Enablingtechnologies
MagnetsHeliumcoolingDiagnos3csFueling/exhaustHeatexchangerTri3umprocessingHea3ng¤tdrive…...
Plasmafacingcomponents/plasmamaterialinterac3onsin1)tokamaks,2)linearplasmadevices,3)offline(e.g.HHF,liquidmetal)integratedPFCtes3ng
Plasmadevelopmentin1)shortpulsetokamaks,2)longpulsetokamaks(EAST,KSTAR,JT-60SA),3)ITER
Integratedlauncher/guidetes3ng
Integrateddiagnos3ctes3ng
Thesmallerintermediatestep(FNSF)onapathtopowerplantsàwhatis
uniqueabouttheFNSFTheenvironmentintheFNSFwillnothavebeenseenbefore,thecombina3onoffusionneutronsandthemul3-physicsnon-nuclearenvironment
40 20 100 8060
dpa
50mm 25mm 0mm
Helium production (appm) for 100 dpa at plasma facing side
15001000500 25
PLAS
MA
VonMisesstress
Temperature.DegC
plasma
94MPa0.6MPa
LiPb,~3MPa
He,8MPa
543C
350C
plasma
Y.Huang,N.Ghoniem,UCLA
DCLLBlanketexample
appmHe
H. Tanigawa, E.Wakai 2012
0.6MPa
94MPa
“SeveralcriMcalmaterialsbehaviorsledtomajordisturbancesinthe
developmentprogramfortheliquidmetalfast
breeder”(Bloometal,JNM2007&Was,JNM2007)
200.0954.5e-42.1e-61.0e-8
Dpa/FPY
Environment:TemperatureStressDamageandHe/Hgenera3onHydrogeninmatrix(HandT)LiPb/RAFMinterface(T,v),chemicalLiPb/SiC-cFCIinterface(T,v),chemicalB-fieldfrom5-12T,OBtoIBforLiPbHea3ng(surfaceandvolumetric)GRADIENTSinalloftheaboveparameters
LMesMmatedcorrosionforaDCLL
Smolentsev,UCLA
Davis,UW
Pulselength,s
100 101 106 107103 104 105102
βN
5
4
3
2
6
PowerPlant
Presentfacili7es
ITER
ACT1
ACT2
Rangeofpowerplants
DEMOJT-60SA
KSTAR
EAST
1day 2weeks 1year
NowallβNlimit
WithwallβNlimit
FNSF
ThePlasmaDura3onsRequiredintheFNSFisaLargeLeapComparedtoPresent/PlannedTokamaks
BeforetheFNSF,mustcombineultra-longpulselinearplasmafacili3estokamakconfinementexperimentsatshorterpulseshighheatfluxfacili3esadvancedpredic3vesimula3oncapability
TakeadvantageoftheDDphaseofFNSFtoextendpulselengths
PhysicsStrategyfortheFNSFRegimeoflongpulse,100%non-induc3ve,burningplasma
PursueβN<nowalllimittoaccomplishmission,butinstallappropriatefeedbackorothercapabilitytoexceednowalllimitàbyhowmuch?
Installpassivestabilizersandfeedbackcoilstoprovidehigherplasmaelonga3on,significantlyexpandingopera3ngspace,andA=4
OperatebelowtheGreenwalddensitylimitn/nGr<1,butnotrelyonlowvaluestoenhanceCD
Plasmacurrentisdriven100%non-induc3velyinflaLop,however,asolenoidprovidesrampupassistanceandflaLopfeedback…examiningNB,LH,ICandEC
Peakheatfluxtoleratedinthedivertor<10MW/m2,whilepursuinghighheatfluxdesign/materialsolu3onsand2DSOL/divertorplasmasimula3ons
Pursuinghightoroidalfieldintheplasma,targe3ngLTSCadvances
NATIONAL FUSION FACILITY
DIII–D
!"#$%&'()%%&'!*+,+-)./,0"'1%#23#2'4.5,"0"-'6,/5'!!'!'7
8' 9,:5'/$,#+:)%#$,/&'-*);%"'+)%%' *<"$#/,*+'#%%*62'*<"$#/,*+'=>?' #;*0"'+*@6#%%'%,3,/
8' ()/)$"'#0#,%#;,%,/&'*A'5,:5"$'BCCD' <*6"$'25*)%-'#%%*6'A)%%&'+*+@' ,+-)./,0"'*<"$#/,*+
157-06/MW/jy
0.0 0.2 0.4 0.6 0.8 1.0Normalized Radius
0.2
0.0
0.2
0.4
0.6
JOHM
Jtot0.8
1.0
(MA
/m2 )
0
1
24!i
!N3
4
0.50.4
0.3
0.2
0.1
0.012.5
10.0
7.5
5.0
2.5
0.00 1 2
Time (s)
3 4
PNBI (MW)
G = !NH89/q95
PECCD (MW)
2
fNI = 90%ITER Q=5 steady-state target
Greenfield, EX/1-2, Mon. p.m.
fNI~90%
DIII-Dexpt
DNdivertorHighradia3ondivertorsolnsMi3gateddisrup3ons
110
500100
ELECTRONTEMPERATURE(eV)
Ver3calPosi3on
(m)
2.5
2.0
1.0
0.5Flat-plate
PlasmaPerformanceandDura5oninDIII-DandJT-60ULookingatExperimentsforGuidance
JT-60U JT-60U DIII-D DIII-D DIII-D DIII-D
βN 2.4 1.7 3.5* >3.5 2.0 3.1-3.4*
τflaLop/τCR 2.8 2.7 2.0 ~1.5 >2 ~0.4-1.0
q95 4.5 ~8 6.7 5.5-6.5 4.7 5.0-5.5
fBS 45% 80% 40-50% 50-60% ~60%
fNI 90% 100% 75% ~100% 80-100%
H98 1.0 1.7 1.0 1.6 1.3 >1.2-1.3
qmin ~1.5 1.5 ~1.0 1.4
~steadystate
steadystate
à steadystate,off-axisNB
à SShybrid,hirot
QH-mode,noELMs
steadystate
*u3lizeac3veerrorfieldcorrec3on,plasmarota3on,βN~1.15xβNnowall
Addi3onalexperimentsonJT-60U,DIII-D,AUGhave1)approachedandexceededdensitylimit,2)highradiatedpowerintheplasmaanddivertor,3)avoidingorac3velysuppressedNTMs,4)lowplasmarotaMon,and5)PFCmaterials
EASTandKSTARwillsooncontribute
A=4R,m 4.80
κX,δX 2.2,0.63
IP,MA 7.87
BT,BTcoil,T 7.5,15.85
<jTF>,MA/m2 15MA/m2
βNth,βNfast 2.2,0.23
q95 6.0
H98 0.99
fBS 0.52
Zeff 2.43
n/nGr 0.90
n(0)/<n>,T(0)/<T> 1.4,2.6
Pfusion,Prad,core,Prad,div,Paux,MW
517,60,160,130
Q,Qengr 4.0,0.86
ηCD,A-m2/W 0.2(assumed)
<Nw>,Nwpeak,MW/m2 1.18,1.75
qdivpeak(OB,IB),MW/m2 10.7,3.9
SystemsCodeIden3fica3on
LargescansoverR,BT,q95,βN,Q,Zeff,n/nGr
<jTF>=15MA/m2
fdiv,rad=90%(λpowFundamenski)Filtersforsolu3ons
βN<2.6*qdivpeak<10MW/m2
Nwpeak>1.5MW/m2
BTcoil<16T(adv-LTSC)
IBRadialbuildfromneutronics:ΔFW/blkt=50cmΔSR=20cmΔVV=10cmΔLTshield=23cmΔgaps=20cm
*examiningbenefitsoffeedbacktoraisethistoward3.0-3.2
Whatisthereliablyachievableradiatedpowerfrac3oninthedivertor?
peak
div
erto
r hea
t flux
, MW
/m2
ave neutron wall load at plasma, MW/m2
βN < 2.6BT
coil < 16 Tqdiv
peak < 10 MW/m2
fdiv,rad = 0.95 0.90 (ref ) 0.85 0.80 0.75
<Nw
> <
1.15
MW
/m2
0.85
MW
/m2
H98
(y,2
) ene
rgy
confi
nem
ent m
ultip
lier
Greenwald density ratio, n/nGr
fusio
n po
wer
, MW
auxiliary power, MW
Weassumearadiatedpowerfrac3onPdiv,rad/PSOLof90%insystemsanalysis
Fullydetachedradiates~100%ITER-likedivertorradiates~75%
SeveralEngineeringDecisions
Lowtemperaturesuperconduc3ngcoils,advancedNb3Sn,withdesignupgradestowindingpack,awatchonHTSC,probablyusingHTSCforCS
Heliumcoolinginblanket,shield,divertor,andvacuumvessel,NOWATERinsideorinVV,onlyoutsideVV
FocusonDCLLblanketconceptwithbackupconcepts(HCLL,HCCB/PB)
NetelectricityisNOTafacilitytarget,butelectricitygenera3oncanbedemonstratedWCusedasshieldingfilleronIBinstructuralring,VVandlowtemperatureshield,B-FSusedforOB,LOCAanalysisshowedthatWCwasOKHorizontalmaintenanceisadopted,singlesectorsareremovedandreplaced(1/16th),superstructuresupportonTFcoillargeouterlegUsedlowerirradia3onlimitsonTFcoilthantypicalforpowerplantstudiesPlaced200micrometersofWontheFWforerosionandtransients(ELMs&disrup3on),whiletryingtoop3mizedesignformaximumheatfluxAssumeconcentricHeandLiPbpipingfromfusioncoretoHXPlatedivertorconceptistungsten(something)structuralandarmormaterial,adv-RAFMforcoldlegstructure,uncertaintyontheformofW
Phase 1 2 3 4 5 6 7 He/H DD DT DT DT DT DT PP years 1-2 2-3 2.75 4.5 5.0 6.5 6.5 40 FPY Nw
peak,MW/m2
1.75 1.75 1.75 1.75 1.75 2.25
Plasmaon-time,%/year
15-50 15 55 d
25 91 d
35 128 d
35 128 d
35 128 d
85 310 d
Plasmadutycycle,%(pulse/dwell)
33 (1d/2d)
67 (2d/1d)
91 (5d/.5d)
95 (10d/.5d)
95 (10d/.5d)
100%
Totalmaintenancetime,days
550 d 200 d/yr
1131 d 229 d/yr
1120 d 224 d/yr
1495 d 230 d/yr
1495 d 230 d/yr
2585 d 55 d/yr
Peakdpa 7.2 19.7 30.6 39.8 79.6 150-200 Max/minblanketstructureoptemp,oC
>400 >400 550/400 550/400 600/450 650/500 650/500 600-650
BlanketStructurematerial
RAFM RAFM RAFM RAFM RAFM-ODS
RAFM-ODS(NS)
RAFM-ODS(NS)
RAFM-ODS(NS)
ProgramontheFNSF–whatisthisdeviceactuallydoing?
TheFNSFProgramisbeingstudiedfurthertoaddressarangeofissues
1) CantheDDPhaseprovideenoughdischarge3merangingfrom1hrto10daypulse
lengths,likelywillu3lizehigherdiagnos3ccoverage
2) Providehigherorlowerneutronwallloadswouldresultinshortorlonger3metoreachadpalevel,e.g.operateabovetheno-wallbetalimit
3) Varyingopera3ngtemperaturesoftheDTphasesmayrequireBOTHfastercoolantflowandlowerfusionpower,longer3metoreachdpatarget,constrainedbyblanketdesignthermo-mechanics
4) Desiretoreachlongestplasmadura3onsearlyintheprogram,ratherthanspendthewholeprogramprogressivelyextendingtheplasmapulselength…appearsadischargesequencecanachievethis,ands3llarriveat~7dpaattheendofthephase
5) Examinemaintenance3mesassociatedwithspecifictasks(plannedmaintenance)Ex-vesselinspec3onIn-vesselinspec3onMinormaintenanceex-vesselMinormaintenancein-vesselMajorex-vesselMajorin-vesselmaintenance(sectorremovalor16sectorremoval)
Con3ngencyforunplannedmaintenance
ChallengesinCrea3ngaProgramontheFNSFFlexibilityinadjus3ngenvironmentalparametersliketemperature,forexample
WanttoexaminearangeoftemperaturestouncoverphenomenaBlanketdesignsaregenerallyop3mizedandthereforeconstrainedUsefusionpower,flowspeedandinlettemperature(forexample),butrangeislikelylimitedSimilarforLaunchersanddivertorsWhatistheflexibilitytoexploretheopera5ngregime?
Howisinforma3onobtainedfromfailures,materialinspec3ons,andopera3ons,usedtocorrect,re-design,andre-manufacturecomponentsorothersystemsforthenext(?)phase….can3me-scalesbeminimizedTheproceduresofstoppingtheplasma,1)butmaintainingcomponentsattemperature,2)removingasinglesectorwhileothersarewarm,....ul3matelyfordescribingmaterialhistoryDoweneedallocatelarger3me,moreintheinspec3on/maintenancecategory,toautopsyandprocessresults,thesamplesarehighlyradioac3ve,butwecannotwaityearstofindoutwhathappenedTheHotCellbecomesacriMcalpartoftheFNSFfacility,wheresectorsareinspected,decontaminated,dismantledandulMmatelyturnedintosamplesforexaminaMon
ComponentsinfusioncorewouldbeevolvedandtestedintheFNSF
IBandOBBlankets
RFLaunchers,TBMs,DiagnosMcsDivertor
Weconcentrateontheblankets,butthereareothersthatmayhaveates3ngsequence…..materials,temperatures,design,etc.
BlanketLayoutandTes3ng
DCLL550/400CRAFM(somearetakenforautopsy) 4DCLL550/400CRAFM/LH 1DCLL550/400CRAFM/EC 1DCLL550/400CRAFM/NB 1DCLL550/400CRAFM/IC 1DCLL600/450CRAFMODS(nextphaseTandRAFM) 2DCLL550/400CRAFM/MTM 1DCLL550/400CRAFM/TBM-HCLL 1DCLL550/400CRAFM/TBM-HCCB(PB) 1DCLL550/400CRAFM/DiagnosMc 3
Step 9 4 TBM added, 4
sectors
Step 10 3 Diagnostics added, 3
sectors
Step 11 2 NBI added, 4
sectors
Step 12 1 IC added, 1
sector
Step 13 1 LH added, 1
sector
Step 14 1 EC added, 1
sector
Nuclearanalysisofdifferentsectors
A.Davis,UW
ThereareseveralDIFFERENTblanketgeometriesduetomul3plefunc3onsintheFNSF
Topview
DivertorTes3ng,mustfitintotheallocatedenvelope
ITER-like3ltedplateFdiv,rad~75%
FlatplatfullydetachFdiv,rad~100%
WhatwillbethepreferredWorotherdivertormaterial?
WorW-alloyW/XcompositesWf/Wmcomposites???
WilltherebevariantslikeRAFM?Structure&armordesignMagne3cgeometriesTemperatureranges
W/RAFlaminate(Garrison) FZJ
WCinFematrix(Álvarezetal.,2015)
X-divertor,KDEMOCovelle,UnivTexasTakenfromSnead,2016
WhatdowedowiththeSectors:Blankets,Divertors,LaunchersintheHotCells?
InspectDecontaminate(cleanoff)InspectDismantleInspectExamineuntreatedsurfacesExaminemounts/connectorsCutsamples
FWSidewallGridplatesMoun3nghardwareSRDivarmorDivstructureFCIWstabilizer…...
MaterialexaminaMons(PIE,mechproptests,Hebubbles,etc.)
Alsoexaminethetestspecimensinthematerialtestmodule&surveillencesamples
HotCellWearean3cipa3ngahotcellsequencefromlargeintactsectorsprogressivelydowntosmallmaterialsamples,requiringatransferfromhotcell1tohotcell2,etc.Robo3candcomputercontrolledsystemswouldlikelydominatetheprocessingIssuesinclude1)highdoseandhardenedequipment,2)complexprocessing(triMum,surfacematerials),3)decayheat,and4)needforrapidturnaround
Fusionneutronmaterialscience
TriMumscience
Plasma-materialscience
Liquidmetalbreederscience
FusionNuclearScienceFacility
2015 2025 2035
LinearPlasma&Tokamaks&Offline
single-feweffects maximumintegra3onexpts
EarlyDDphaseofFNSF
par3alintegra3onexpts
PredicMveSimulaMonDevelopment
AcceleratorbasedfaciliMes
FusionneutronandintegratedcomponenttesMngfaciliMesconMnuetooperateinparallelwithFNSF
IntegraMonofFW/blanket
Enablingtechnologies(H/CD,fueling,pumping,…..
Pre-FNSFR&DMajorTopicsandEvolu3onTowardFNSF
Fusionneutronmaterialscience
TriMumscience
Plasma-materialscience
Liquidmetalbreederscience
FusionNuclearScienceFacility
2015 2025 2035
LinearPlasma&Tokamaks&Offline
single-feweffects maximumintegra3onexpts
EarlyDDphaseofFNSF
par3alintegra3onexpts
PredicMveSimulaMonDevelopment
AcceleratorbasedfaciliMes
FusionneutronandintegratedcomponenttesMngfaciliMesconMnuetooperateinparallelwithFNSF
IntegraMonofFW/blanket
Enablingtechnologies(H/CD,fueling,pumping,…..
Pre-FNSFR&DMajorTopicsandEvolu3onTowardFNSF
HowdoIturntheseTOPICSintoaconcretesetofexperimentsthatgetmetotheFNSF?Integrateandmakeprototypical
TriMumscience FusionNuclearScienceFacility
2015 2025 2035single-feweffects maximumintegra3onexptspar3alintegra3onexpts
PredicMveSimulaMonDevelopment
IntegraMonofFW/blanket
Plasmatri3umimplanta3on/permea3on/reten3on
Tri3umbehaviorinmaterialsandmul3-materials
Tri3umextrac3onfromLiPbbreeder
Tri3umbreeding/extrac3onfissionintegratedexpt
Zoom–In:Tri5umScienceBreakdown
Plasmatri3umimplanta3on/permea3on/reten3on
- PISCESatUCSDandTPEatINL,exis3ngexpts- Characterizeitsparametersrela3vetoaFNSForDEMO(par3cle
energies,fluxes,par3clespeciesandmixtures,opera3ngtemperatures,tes3ngdura3on,in-situsurfacediagnos3cs,etc.)
- CapabilitytotestHecooledcomponentgeometry,tes3ngirradiatedsamples
- In-situmeasurementsinlongpulsetokamaks
Tri3umextrac3onfromLiPbbreeder
- Nofacilityatpresent(dowithdeuteriumasmuchaspossible?)- RequiresaLiPbloop,runningthroughatubulartestremovalapparatus- Ar3ficiallyintroducedeuterium,andcontrol/characterizeLiPbmaterial- Musttestdifferentpermea3onwindowmaterials(group5,modified
group5asnotedbyINL)- Parametersincludeopera3ngtemperature,flowrates,hydrogen
concentra3ons,impuri3esinLiPb,etc.- Scale-uptomul3-tube
Tri3umbreeding/extrac3onfissionintegratedexpt
Usingfissionfacilitytoaccesslargervolumefortes3ngCreateaseriesoftestar3clesthatincludeRAFMsteel,SiC-c,flowingHe,andLiPb
Sta3onaryLiPbFlowingLiPb
Testsofdpa(exposure),Li6fortri3umbehavior,temperature,flowratesforLiPb
Tri3umbehaviorinmaterialsandmul3-materials
- Tes3ngapparatusforsinglematerials(solids)characterizingwithHeat8MPa,vacuum,LiPbat~3MPa
- LiPbpris3ne,andLiPbwithHebubbles,intermetallics,corrosionproducts- atrepresenta3vetri3um/deuteriumconcentra3ons- attemperatures,tendingtowardserviceenvironment- accuratesurfacecondi3oncharacteriza3on- irradiatedmaterials- RAFM/LiPb,RAFM/SiC-c/LiPbmul3-materialtests
Theseexperimentsleadintotheintegratedblankettes3ngfacility
FusionNuclearScienceFacility
2015 2025 2035single-feweffects maximumintegra3onexptspar3alintegra3onexpts
PredicMveSimulaMonDevelopment
Zoom-In:FusionNeutronMaterialScience
Non-nuclearmaterialcharacteriza3onandindustrialproduc3on
Fissionneutron,ionanddopingmaterialexposure
Fusionrelevantneutronmaterialexposure
Fusionneutronsmaterialsscience AcceleratorbasedfaciliMes
Mul3-material/environmentfissionneutronexposure
ThisR&DgenerallydoesNOTintegratesignificantly
HFIR,ATR
SNS,LANSCE,USSINQ,DONES,EUA-FNS,JA
HFIR,ATR
Pre-FNSF:FusionNuclearMaterialsScience,howdoweseeprovidingtestedmaterialsintheformofcomponentstotheFNSF
2020 2030 2040 2050 2060
FNSFUSDEMO
PreFNSFRAFM-1development
PreFNSFFCI/SiC-c-1development
PreFNSFbaini3cdevelopment(VV)
PreFNSFtungsten-1development
He/DD DT
7dpa 19dpa 30dpa 40dpa 40-80dpa
PreFNSFRAFM-2development
PreFNSFRAFM-3development
PreFNSFRAFM-4develop
PreFNSFtungsten-2development
#ofsamplesofmechtype#temperatures#materialsTestvolDpa/FPYAvailabilityàWhattypeofdatabaseisrequiredforFNSF?ScienMficorengineering?
Aquan3ta3veanalysisofasingleblanketconceptcouldmaketheurgencycaseforge~ngtofusionrelevantneutronsNOW
PreFNSFFCI/SiC-c-2development
Non-nuclearcharacteriza3onFission,ionanddopingirradia3onsFusionrelevantneutronirradia3onsIndustrial/manufacturingMaterial/environmentmatch
SOLplasmaexperiments/diagnos3cs
Divertorplasmaexperiments/corecoupling
Plasmamaterialinterac3on/linear/ultra-longdura3on
Highheatfluxsimulators(ebeams,lasers,flashlamps,etc.)
tokamaks
Solidmaterialsscience,PFCcomponentdesignandfabrica3on
LoadingcondiMons
Liquidmetalteststands,plasma/vacuum,LMproper3es,flow,geometry,LMspecies,substratedesignandfabrica3on,etc
TesMngofPFCcandidatesinlinearandtokamakfaciliMes
Establish“transla3on”oflinearresultstotokamaks
Star3ngpointfororganizingthepre-FNSF:PFC/PMIscienceareafromtheFNSFperspec3ve
SOL/divertorplasmasimula3ons
MaterialsscienceandPFCcomponentdevelopment
Plasmascience
PMIscience
FusionNuclearScienceFacility
2015 2025 2035single-feweffects maximumintegra3onexptspar3alintegra3onexpts
PredicMveSimulaMonDevelopment
LTSCadvance/op3mize,HTSCdevelopment
Pelletfueling,exhaustandcon3nuousvacuumpumping
Heatexchangerdevelopment
Zoom–In:EnablingTechnologyBreakdown
Enablingtechnologies
Hea3ngandcurrentdrivesources,launchers,transmission,coupling
Diagnos3csforFNregime,physicsandengineering
Tri3umprocessingforbreedingandfuelingcycles,storage
HotCellhandling,processes,PIE
…..........
DetailedAnalysisinEngineeringandPhysicsoftheFNSF
Neutronics,1Dthisyeartodevelopbuildsandhea3ng,3Dnextyearformoreaccuracy,streamingandotherissues(A>Davis,L.El-Guebaly,UW)
LiquidmetalMHDanalysisbySmolentsev(UCLA)onIBandOBLiPbflow
Thermo-mechanicsofblanket,FWanddivertorbyY.Huang/N.Ghoniem(UCLA),J.BlanchardatUW,S.Malang(re3red),M.Tillack(UCSD)
TFcoil(andPF)coilsstressanalysisandwindingpackdesignbyY.Zhai,P.Titus(PPPL)
Tri3uminventory,extrac3onanalysis(andaccident)byP.Humrickhouse(INL)
MaterialssciencedevelopmentandassessmentsbyFusMatgroupatORNL(A.Rowcliffe,L.Garrison,andY.Katoh)
CAD,establishinglayoutsforFNSFfromsystemscodeanddesignac3vi3es(E.MarrioL)Maintenance,hotcell,layout(L.Waganer)
Coreplasmaequilibrium,idealstability,3me-dependenttransportevolu3on,H/CD(C.Kessel,PPPL)
SOL/divertoranalysis,(RognlienandRensink,LLNL)RFrequirements(G.WallaceandS.Wukitch,MIT/PSFC)
TheFNSFHasaUniqueRoletoPlayinBreakingintotheFusionNuclearRegime
Introducesthecombinedfusionnuclearandmul3-physicsnon-nuclearenvironmentonfusioncorenotseenbeforeAdvancesthemul3plemissionsrequiredtoreachapowerplantopera3ngspaceOperatesawiderangeofenablingtechnologies(in-VV,ex-VV…)Developstheultra-longplasmadura3ons,plasmasupporttechnologies,andplasmaperformanceforthestrongfusionnuclearregimeAcarefulanddeliberatestepisrequiredforthischallengingleapTheFNSFisacombina3onofdiscoveryanddemonstraMon,andul3matelyprovidesthedatabaserequiredtopursuefusionenergybasedpowerplants
BACKUPSLIDES
Dpa/fpy
NWLmap
3DCAD,LHlauncher
TBRwithallpenetra3ons
TBRwitheachpenetra3ontype
1.067NuclearAnalysis A.Davis,UW
Neutronhea3ng
minimal moderate maximal Power plant Plant DT operations
~ 15 yr ~ 25 yr ~ 35 yr 47 yr (40 FPY)
Peak neutron wall load, MW/m2
1.0 1.5 2.25 2.25
Plasma on-time per year
10-35% 10-35% 10-45% 85%
Max dpa on first wall (or max dpa to replace)
5 -18,36 7 - 37,74 10 - 70,140 150-200
Qengr << 1 < 1 > 1 4 Tritium breeding ratio
< 1 ~ 1 > 1 1.05
Plant life, peak dpa
50 126 274 765
TF/PF magnet Cu LTSC or HTSC LTSC or HTSC LTSC or HTSC Vacuum vessel material
SS Baintic steel Bainitic steel Bainitic steel
Divertor W/CuCrZr/H2O W/W/He W/W/He W/W/He
LargedeparturefromPP
Somedeparture
Smalldeparture
SystemsanalysisofMinandMaxFNSF
FNSF Min Mod Max
R,m 3.5 4.8 5.8
Ip,MA 6.38 7.87 8.04
BT,BTcoil,<jTF>
5.75,13.5,14.7
7.5,15.9,15.0
8.0,15.7,15.0
βNth,βNfast 2.3,0.1 2.2,0.23 2.3,0.36
q95 5.5 6.0 7.5
H98 0.95 0.99 1.13
fBS 0.53 0.52 0.66
n/nGr 0.9 0.9 1.0
Pfusion,Paux,MW
185,92.5 518,129 754,116
Q,Qengr 2.0,0.51 4.0,0.86 7.0,1.11
<Nw>pl,Nw
peak,FW0.71,1.0 1.19,1.67 1.21,1.7
qdivpeak 6.0 10.7 9.88
ΔIBtoTFcoil,cm
87(includesCS)
123 129
CuTF/CS/PF ηth=0.35
qdivpeak<10MW/m2βNtotal<0.026BTcoil<16TηCD=0.2A/W-m2Sameplasmashapefdiv,rad=0.9SmallestradiuswitharobustopspaceMinR=3.5mModR=4.8mMaxR=5.8m
Fusionneutronsmaterialscience
Tri3umscience
Plasma-materialscience
Integratedblankettes3ngLiquidmetalbreederscience
Enablingtechnologies(H/CD,fueling,pumping,diagnos3cs,magnets,BOP)
DEMOFNSF
DT DT DT DT DTDD
Predic3vesimula3on
Zoom-Out:ExaminetheR&DFlowOverPre-FNSF,FNSF,andintoDEMO