may 1-3, 2001 engineering - the fire placeimplications of li divertor and other liquid-metal...
TRANSCRIPT
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Implications of Li divertor and otherliquid-metal technologies
D.N. Ruzic and J.P. Allain
Department of Nuclear, Plasma and RadiologicalEngineering
University of Illinois, Urbana-Champaign
UFA Burning Plasma Science Workshop IIGeneral Atomics, San Diego, CA
May 1-3, 2001
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Outline of Talk
hThe walls as the problemhThe walls as the solutionhCurrent efforts in plasma facing component
science and technologyhEnabling technologies for existing/future
fusion deviceshConclusionshAcknowledgements
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Many of fusion’s problems involveplasma wall interactions
hCheaper electricity means higher powerdensity and therefore more power towalls.
hDisruptions (unplanned and planned)severely limit lifetime and thereforedesirability.
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NC ARIES-RS Design Module
C.P.C. Wong, et al. “Toroidal reactor design as a function of aspect ratio”
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SC ARIES-RS Design Module
C.P.C. Wong, et al. “Toroidal reactor design as a function of aspect ratio”
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Lithium on surfaces could solve theseproblems and have other benefits
h Flowing liquid plasma-facing systems canrapidly remove heat.
hContinuous recovery of damaged surfacesexposed to large heat fluxes due to off-normalevents as well as disruptions.
h TFTR Li pellet and DOLLOP experiments
h Possible stabilization of MHD modes bysubstituting a moving conducting wall forplasma rotation
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TFTR Results: Li conditioning
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Li conditioning effect on nτeT
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TFTR Results
D.K. Mansfield, PPPL, ALPS/APEX Albuquerque, NM 2000
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TFTR DOLLOP Results
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Disruptions set severe limits onITER-FEAT
hVDE (verticaldisplacement event60 MJ/m2 for 300mson first wall
hThermal quench 30MJ/m2 in 1 ms ondivertor
G. Federici, et al. J. Nucl. Mater. 290-293 (2001) 260.
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Net erosion of ITER divertor
J. Brooks, D. Alman, G. Federici, D.N. Ruzic and D.G. WhyteJ. Nucl. Mater. 266-269 (1999) 58.
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ELMs set power limit even for W
G. Janeschitz, et al., J. Nucl. Mater. 290-293 (2001) 1-11
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Plasma Facing Component Science andTechnology Program
• Integrated concepts
• Lab-scale investigations
• Modeling efforts
• Near-term experiments
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C.P.C. Wong, et al. “Exploration of Innovative Advanced Solid Wall Concepts” presented at:U.S. Fusion Chamber Technology Peer Review, UCLA, April 26, 2001
Flowing Li dropletdivertor
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Flowing lithium droplet divertorcassette
R.F. Mattas, “ALPS – advanced limiter-divertor plasma-facing systems”” Fusion Engineering and Design 49-50 (2000) 127-134
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CLiFF(Convective Liquid
Flow First-Wall)
N. Morley, et al. APEX Interim Report, UCLA-ENG-99-206, Nov 1999
Conceptual sector schematic ofCLiFF implementation in ARIES-RSreactor
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CLiFF – Flow/Temperature Schematic
N. Morley, et al. APEX Interim Report, UCLA-ENG-99-206, Nov 1999
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IIAX (Ion-surface InterAction eXperiment)
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In-situ cleaving arm design and HVheaterhCleaving arm is
designed to removethin oxide layerformed on Li layer ofliquid tin-lithium orliquid lithium sample
hSurface compositionexperiments showthat Li segregates tothe liquid Sn-Lisurface1
A HV heater was installed insidea BN cup.
TC
QCM-DCU
Plasma cup
1. B. Bastasz J. Nuclear Mater. 290-293 (2001) 19.
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Secondary ion fraction and deuterium-saturation studies of liquid metals in
IIAX at UIUC
102 103 1040.00
0.25
0.50
0.75
1.00
Sec
onda
ry io
n sp
utte
ring
frac
tion
(spu
tterin
g io
ns/ s
putte
red
atom
s)
Incident particle energy (eV)
Secondary Li ion fraction (non D-sat.) Secondary Li ion fraction (D-saturated)
h Saturation of solid and liquid (T/Tm ~ 1) tin-lithium with D atomsresults in no effect on the absolute sputtering yield of lithium.
h Ion fraction measurements show that 55-65% of sputtered atomsfrom D-saturated solid and liquid lithium are in an ionized state.
102 10310-2
10-1
100
Abs
olut
e S
putte
ring
Yie
ld o
f Li (
atom
s/io
n)
Incident particle energy (eV)
D-treated Liquid 0.8 Sn-Li non D-treated solid 0.8 Sn-Li D-treated solid 0.8 Sn-Li
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IIAX experimental and modeling data onliquid lithium erosion
hD treatedlithium yieldsare well belowunity
hData taken at45 deg.Incidence and200 C surfacetemperature 101 102 103
10-2
10-1
100
Abs
olut
e S
putte
ring
Yie
ld (
a.u.
)
Incident particle energy (eV)
Li+ on liquid Li (IIAX data) VFTRIM-3D, Li on liquid phase Li He+ on liquid Li (IIAX data) VFTRIM-3D, He on liquid phase Li D+ on liquid Li (IIAX data) VFTRIM-3D, D on liquid phase Li
J.P. Allain, M.R. Hendricks and D.N. Ruzic, J. Nucl. Mater. 290-293 (2001) 180
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Effect of deuterium surface treatmenton lithium erosion
102 10310-2
10-1
100
Abs
olut
e Li
spu
tterin
g Y
ield
(Li
par
ticle
s/ io
n)
Incident particle energy (eV)
He+ on non D-sat Li He+ on D-sat Li He+ on D-sat Li (neutrals only)
J.P. Allain and D.N. Ruzic, Nucl Fusion, submitted 2000
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FLIRE concept
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FLIRE (Flowing Liquid Surface IllinoisRetention Experiment)
hFLIRE will providefundamental data onthe retention andpumping of He, H,and other gases inflowing liquidsurfaces.
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PMI Experimental efforts in ALPS
B. Bastasz, et al. SNLL
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PISCES – glowing lithium
R. Doerner, et. al., J. Nucl. Mater. 290-293 (2001) 166.
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DiMES
R
BT
0 2 4 6
1015
1014
1013
time (s)
1
10
Te(eV)
ne(cm-3)
Private-fluxPlasma Incident on
Lithium / DiMES
h Lithium is sputtered in private flux (PF) plasma
by charge-exchange neutrals
h Neutral lithium resonance line (670 nm, Ehν~2
eV) is easily excited by Te~1 eV PF plasma.
h Lithium is quickly ionized in very cold, dense
PF plasma!
Private fluxplasma at DiMES
ionization potential (eV)
2S 2P 2D
0
1.8
5.4
3.4 460 nm
671 nm
Li I Energy LevelDiagram
Li I Light from DiMESduring PF exposure
D.G. Whyte, et. al., UCSD and General Atomics
Lithium provides a unique opportunity to study erosion and
transport in the private flux region due to its ease of erosion &
excitation.
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A * T H E R M A L - S ( T h e r m o d y n a m i c s / H e a t
T r a n s f e r / M H D / R a d i a t i o n T r a n s p o r t )
L i q u i d - L a y e r S p l a s h / B r i t t l e D e s t r u c t i o n
S P L A S H S U P E R A T O M
P h D ( P h o t o n D e p o s i t i o n )
( A t o m i c P h y s i c s )
D R D e p ( D e b r i s D e p o s i t i o n )
S i m u l a t i o n P a c k a g e f o r H i g h E n e r g y
I n t e r a c t i o n w i t h G e n e r a l
H e t e r o g e n e o u s T a r g e t S y s t e m s
I T M C ( M o n t e C a r l o / E n e r g y D e p o s i t i o n )
T R I C S ( T r i t i u m D i f f u s i o n )
H E I G H T S P a c k a g e
S O L A S ( S c r a p e - O f f L a y e r )
T R A P ( D i f f u s i o n i n
P o r o u s S t r u c t u r e )
P H I L T ( P u l s e d
H y d r o d y n a m i c s )
S W H I F T ( S h o c k W a v e H y d r o d y n a m i c s )
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A. Hassanein and I. Konkashbaev, J. Nucl. Mater. 273 (3) (1999) 326.
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Plasma-liquid surface interaction Modeling(cont.)
T. Rognlien and M. Rensink,LLNL
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Plasma-liquid surface interaction Modeling(cont.)
Electron temperature in outer scrape-off layer forthe UEDGE plasma solution with low-recycleliquid lithium divertor
Gross and instantaneous (before liquid flow)net erosion rates from WBC code
J. Brooks, et al. J. Nucl. Mater. 290-293 (2001) 185
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NSTX: application of flowing liquid metal(i.e. ALIST)
B. Nelson and P. FogertyAPEX Task I
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Conclusions
h Plasma interactions with the surfaces limit thedesirability of fusion power
h Advances in fusion science and performanceoften follow new surface-related discoveries
h Wall concepts involving Li show great potentialto solve many known problems
h ALPS and APEX programs are actively engagedin pursuing these solutions
h Planned burning plasma devices shouldconsider including these – they may just bewhat makes it work.
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Acknowledgements
hDOE ALPS Program (Advanced Limiter/Divertor Plasma-facing Surfaces)
hRichard Mattas
hArgonne National Lab
hUFA for the invitation to speak