Update 2015 on target fabrication requirements for NIF
Transcription
Update 2015 on target fabrication requirements for NIF
Update 2015 on target fabrication requirements for NIF layered implosions, with emphasis on capsule support and oxygen modulations in GDP S. W. Haan,1 D.S. Clark,1 S.H. Baxamusa,1 J. Biener,1 L. Berzak Hopkins,1 T. Bunn,1 D.A. Callahan,1 L. Carlson,3 T.R. Dittrich,1 M.J. Edwards,1 B.A. Hammel,1 A. Hamza,1 D. E. Hinkel,1 D.D. Ho,1 D. Hoover,3 W. Hsing,1 H. Huang,3 O.A. Hurricane,1 O.S. Jones,1 A.L. Kritcher,1 O.L. Landen,1 J.D. Lindl,1 M.M. Marinak,1 A.J. MacKinnon,1 N.B. Meezan,1 J. Milovich,1 A. Nikroo,1 R. Olson,2 L. Peterson,1 P. Patel,1 H.F. Robey,1 J.D. Salmonson,1 V. Smalyuk,1 B.K. Spears,1 M. Stadermann,1 S.V.Weber,1 J.L. Kline,2 D.C. Wilson,2 A.N. Simakov,2 and A. Yi2 1Lawrence Livermore National Laboratory, Livermore, CA 94550, USA 2Los Alamos National Laboratory 3General Atomics (with my apologies for not including in abstract) 21st Target Fabrication Meeting Las Vegas, Nevada June 23, 2015 Summary/Outline We are making good progress toward ignition, and target fabrication is a vital ingredient For the three shotsprogress we have considered in detail, simulations show rough agreement with the data but not a perfect match This 3D simulation by Dan Clark of shot N120321 nicely shows the issues keV N120321 t = 22.85 ns (bang time) g/cm3 4.0 500.0 3.0 375.0 2.0 250.0 1.0 125.0 0.0 0.0 fuel-ablator interface fill tube defect tent defect LawrenceImploded Livermore National Laboratory shape at bang time Green surface = fuel-ablator interface Temperature on left, density on right We are incorporating our most upTent understanding feature is 2-3x bigger to-date of the role than we 1-2 years ago ofrealized the tent, hohlraum drive asymmetries, and other perturbation sources into 2-D and Global out-of-round from 3-D simulationsasymmetry of NIF implosions hohlraum While we do not match all of the Shorter wavelength irregularities data within the error bars, there is are agreement probably for bigger than rough both low andshown, high foot shots, and heavily because of “clean” oxygen nonuniformity mixed shots in GDP The precise effects of the tent and The program is working to hohlraum asymmetries are minimize these drivers features and their probably the biggest for the remaining growthdiscrepancies and impactand subjects for continuing work Developing other options is also important: High Density Carbon, Be, other hohlraum designs 6 2 We believe that we have a fairly good understanding of the issues in CH implosions Dan Clark post-shot modeling for N120321 (characteristic of 2012 NIC “low-foot” shot) with various combinations of degradation factors When everything we know 1000 about is included (in 3D) we get pretty close to the experiment Neutron 100 yield / For the three shots we have considered in 15 simulations show rough agreement with t 10 10 not a perfect match keV 1 N120321 t = 22.85 ns (bang time) g/cm3 4.0 500.0 3.0 375.0 2.0 250.0 1.0 125.0 0.0 0.0 fuel-ablator interface fill tube defect tent defect We are inco to-date unde of the tent, h asymmetries perturbation 3-D simulati While we do data within t rough agree high foot sho mixed shots The precise hohlraum as probably the remaining d subjects for Lawrence Livermore National Laboratory D. S. Clark, M. M. Marinak, C. R. Weber, D. C. Eder, S. W. Haan, B. A. Hammel, D. E. Hinkel, O. S. Jones, J. L.Milovich, P. K. Patel, H. F. Robey, J. D. Salmonson, S. M. Sepke, and C. A. Thomas, Radiation hydrodynamics modeling of the highest compression inertial confinement fusion ignition experiment from the National Ignition Campaign, Physics of Plasmas 22, 022703 (2015) 3 The tent has the most impact on simulated performance Dan Clark post-shot modeling for N120321 (characteristic of 2012 NIC “low-foot” shot) with various combinations of degradation factors 1000 Neutron yield / 1015 100 For the three shots we have considered in simulations show rough agreement with t not a perfect match 10 keV 1 N120321 t = 22.85 ns (bang time) g/cm3 4.0 500.0 3.0 375.0 2.0 250.0 1.0 125.0 0.0 0.0 fuel-ablator interface fill tube defect tent defect We are inco to-date unde of the tent, h asymmetries perturbation 3-D simulati While we do data within t rough agree high foot sho mixed shots The precise hohlraum as probably the remaining d subjects for Lawrence Livermore National Laboratory Tent is the most important single issue. 3-4x bigger than originally expected. In-flight backlit implosion experiments confirm big perturbation. S. R. Nagel, S. W. Haan, J. R. Rygg, C. Aracne-Ruddle, M. Barrios, L. R. Benedetti, D. K. Bradley, J. E. Field, B. A. Hammel, N. Izumi, O. S. Jones, S. F. Khan, T. Ma, A. E. Pak, K. Segraves, M. Stadermann, R. J. Strauser , R. Tommasini, and R. P. J. Town , Effect of the mounting membrane on shape in inertial confinement fusion implosions , Physics of Plasmas 22, 039902 (2015) 4 in base units of centimetres, grams, and kiloelectronvolts. For N130927, fa 5 0.68–0.82. The energy deposited in the hotspot by a-particles is Ea 5 faEfusion/5, recalling that one-fifth of the D–T fusion energy is emitted in the form of a-particles (the remaining a-particle energy is deposited into the cold fuel). We note that, using the values found in Table 1, Ea/Ehs < 0.56. These energies fully describe the hotspot, but part of the implosion energy was used to compress the remaining cold D–T fuel and so we must examine the fuel to get a full picture of the implosion energy balance. Because the D–T hotspot is formed by ablating the inner surface of the cold D–T fuel as electron conduction transports heat from the forming hotspot into the fuel, we can calculate the amount of D–T fuel remaining after the hotspot has formed because we know the bang-time) assuming that the cold fuel and the hotspot are isobaric 5=3 (Pfuel < Phs), in which case we find that a~Pfuel =PF <Phs =0:0021rfuel 5 2.9–3.3 for N130927—the fuel adiabat in flight is lower than this range of values. The fuel density is also needed to calculate the X-ray losses through the fuel. As the hotspot is compressed to high temperatures, the primary energy loss mechanism is bremsstrahlung X-ray emission because the D–T hotspot is optically thin to these X-rays. The bremsstrahlung energy loss is calculated to be24 pffiffiffiffiffi Ebrems (kJ)~5:34|10{34 n2hs Te Vhs tx The tent-seeded perturbation is considerably smaller in less unstable implosions with different pulse shapes Figure from Riccardo Tommasini’s paper analyzing the tent feature in base units of centimetres, kiloelectronvolts and seconds. For N130927, as seen in backlit implosions (“2D ConA” experiments) E 5 2.3–4.5 kJ, the low end of which is nearly equivalent to the 15 Self-heating yield/ compression yield 20 1.5 Yield (kJ) RESEARCH RESEARCH LETTER LETTER RESEARCH LETTER 10 Yield from fuel compression Yield from self-heating Energy delivered to D–T fuel N130710 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 GLC 30° 30° 44.5° 44.5° 30° b b b Inner Inner cone cone Inner cone 23.5° 23.5° 23.5° 44.5° 50° 50° 44.5° 44.5° 50° 44.5° 50° 50° 50° 23.5° 23.5° 23.5° 30° 30° Outer Outer cone cone 44.5° 30° 44.5° Outer cone 44.5° 44.5° 50° Low foot 44.5° 50° 44.5° 50° Shot Shot N130927 Shot N130927 N130927 D–T ice ice layer layer D–T D–T ice layer 2.263 mm mm 2.263 2.263 mm CH ablator ablator graded graded CH 2% Si doped doped CH2% ablator graded Si 110608 110615 110620 110826 110904 110908 110914 111103 111112 111215 120126 120131 120205 120213 120219 120311 120316 120321 120405 120412 120417 120422 120626 120716 120720 120802 120808 120920 130331 130501 130530 130710 130802 130812 130927 131119 0 0 0 N131119 N130927 N130812 N130501 a a a 5 High foot Low foot High foot 1.0 0.5 brems 2% Si doped Cryogenic Cryogenic cooling cooling ring ring Cryogenic cooling ring Shot number This is one reason (possibly the main reason) why high-foot shots have done so well, providing 10x more yield and a lot of nice positive press (eV) Trad TTrad (eV) rad(eV) Figure 3 | Yield and energetics metrics for shots on the NIF. Total fusion lines, 1s) as calculated from the model of ref. 25. The plot shows that, even with yield is plotted versus shot number (that is, time). Shots 110608–130331 are the uncertainty in our results, shots 130927 and 131119 both yielded more c c 300 300 delivered to the N130927 low-foot shots. Shots 130501–131119 are high-foot shots. The bars showing fusion energycthan was D–T. Inset, ratio of self-heating yield to Au N130927 Au hohlraum hohlraum 300 3 shock shock total yield are broken into components of yield coming from a-particle selfcompression yield versus generalizedN130927 Lawson criterion (GLC). All error bars, 3 Au hohlraum 3 shock heating and yield coming from compression. The black dashes denote the 1s. 200 energy delivered to the D–T (fuel plus hotspot) with error bars (black vertical 200 200 Laser Laser entrance Laser entrance hole hole High foot foot High All rights reserved ©2014 Macmillan Publishers entranceLimited. hole 100 100 High foot 100 3 4 6 | N AT U R E | VO L 5 0 6 | 2 0 F E B R U A RY 2 0 1 4 Laser Laser quads quads Laser quads N110914 N110914 4 shock shock N110914 4 4 shock Low foot foot Low 0.0 Low foot 0.0 0.0 5.0 10.0 15.0 5.0 10.0 15.0 0.00.0 0.0 5.0 10.0 (ns) 15.0 tt (ns) 20.0 20.0 20.0 t (ns) Figure 1 | Indirectly driven, inertially confined fusion target for NIF. fuel layer and surrounding CH (carbon–hydrogen) plastic ablator. c, X of b, X-ray the capsule for N130927 with D–T plastic capsule with bundles incident the inside surface of the the hohlraum. hohlraum. b, representative X-ray image image of oflaser the actual actual capsule foron N130927 with D–T of the hohlraum. b, X-ray image of the actual capsule for N130927 with D–T post-NIC high-foot implosion. Figure 1in | Indirectly driven, inertially confined fusion target for NIF. Nature fuel layer and surrounding CH (carbon–hydrogen) plastic ablator. c, X O. A. Hurricane et al., Fuel gain exceeding unity an inertially confined fusion implosion, 506, a, NIF target showing aa cut-away of gold drive temperature CH versus time for for the the NIC NIC low-foot low-foot implosion Figure 1 | Indirectly driven, inertially fusion target for NIF. and fuel layer and surrounding (carbon–hydrogen) plastic ablator. c, X a, Schematic Schematic NIF ignition ignition target showingconfined cut-away of the the gold hohlraum hohlraum and radiation radiation drive temperature versus time implosion plastic capsule with representative laser incident the inside high-foot implosion. a, Schematic NIF ignition target showing a cut-away of theon and post-NIC radiation temperature versus time for the NIC low-foot implosion 343–348 (20 February 2014) plastic capsule with representative laser bundles bundles incident ongold thehohlraum inside surface surface post-NICdrive high-foot implosion. 13–16 13–16 the hohlraum . Although the hotspot shape changes that result 5 through wavelength changes alone, and physical changes to the Final amplitude with adiabat shaping Tent expectations as of May 2015: tents can work, but will require progress on several fronts Smallest possible ring for respective thicknesses, from target fab measurements 110 nm, 8-10° contact angle 45 nm, 10-15° 15 nm, 15-20° Max allowed assuming optimized Adiabat-Shaping pulse shape Max allowed with old low-foot pulse 15 nm, 3-5° contact angle Radius of contact ring 45° ~ 890µm Depends on thickness, contact angle, length of contact ring, and pulse shape • It is unlikely that >20nm tent thickness would be OK • 15nm or less could be OK but we need to push on all fronts: Ø Reduce rms by ~30% with smaller contact ring Ø Reduce contact angle reduces impact by ~1/2 Ø We will need an optimized AdiabatShaping pulse shape that reduces tent growth by ~2x Ø Impact can be evaluated and optimized with HGR experiments, exploring pulse shape and tent parameters 6 A variety of other support options are being explored Capsule can be supported in several ways, each with pros and cons We now have one fill tube, with impact that’s noticeable but smaller than tent. Three or four 10 µm tubes (stalks) might be ~ equiv to 15nm tent. Impact grows with diameter, 30 µm diameter looks scary Line support has considerable length that’s close to the capsule, probably has to be sub-micron (hundreds of nm would be good) Supported fill tube might support capsule with just existing tube touching the capsule Foam Tent, or foam to hohlraum wall Foam support looks good on paper, will depend on uniformity of foam and other details of density and composition My best guess right now (and it is a guess) is that the best tent will be better than foam support, and better than 30µm stalks. Two or three 10 micron stalks would probably be better than best tent. Foam needs to be tested. 7 Tent is probably much less important for HDC and Be Higher density of ablator (and lower opacity for Be) makes capsule ablation pressure higher, pressure wave from exploding tent is relatively less important We have seen a tent feature in a couple of HDC symcaps (esp DT 4-step symcap N130628) but in general it’s much smaller than in CH, in both simulation and expt Simulation work is ongoing, but we expect tent to be 2-3x less important, even better for Be. Does not mean 100nm tent with any pulse shape is OK! But finding a solution will be easier and tent will probably be OK. Also, many near-term experiments with CH can use thicker tents (lowgrowth pulses like Near Vacuum Hohlraums, 2-shock pulses) In the long run, NIF Ignition will require thin tents and accompanying optimization, or some better support strategy 8 Hohlraum drive asymmetry has the 2nd largest impact 1000 Neutron yield / 1015 100 For the three shots we have considered in de simulations show rough agreement with the d not a perfect match 10 1 keV N120321 t = 22.85 ns (bang time) g/cm3 4.0 500.0 3.0 375.0 2.0 250.0 1.0 125.0 0.0 0.0 fuel-ablator interface fill tube defect tent defect We are incorpora to-date understa of the tent, hohlr asymmetries, an perturbation sou 3-D simulations o While we do not data within the e rough agreemen high foot shots, “ mixed shots The precise effec hohlraum asymm probably the bigg remaining discre subjects for cont Lawrence Livermore National Laboratory Another important related issue is hohlraum efficiency (~15% deficient in gas-filled hohlraums, implicit in Dan’s post shot model) This is driving work on a variety of hohlraum options—rugby shape, near-vacuum fill, various sizes, U w/out Au coating 9 DT DT DU hohlraums drive in the preheatclean band (“Mclean reduce mass mass frac. = 0.99 frac. = 0.93 band”), part of optimizing the HDC design “nominal” M-band, all surfaces to unlined DU) 0.7 x M-band,(equiv all surfaces g/cm3 HDC HDC density density DT DT 2-shock Quantitative modeling of the mix un-doped dependsHDC on accurate clean mass mass knowledge of M-band fraction and roughness seeds clean frac. = 0.75 frac. = 0.97 2-shock un-doped design" surface roughness power spectra" Clark—HDC Design Mini-Workshop 08/23/2013 0.7 x " M-band" “nominal” 24% M-band" 18 Dopant in ablator is the other knob controlling this instability growth For HDC, dopant options are limited and unlined DU hohlraums are a big help 10 Irregularities in CH oxygen seed hydro instabilities at a level that is important to NIC performance There is no conclusive proof of this yet, but there are several very persuasive strands of evidence 2±0.005 at% ~2-5 at% We know there is ~0.5 at% oxygen in our CH, ramping up to 2-5 at% at the outside, but know little about transverse uniformity 30µm scale length 0.5 at% Oxygen in GDP. Lateral variations “immeasurably small,” too small to see in a plot like this. 0.01%? Snapshot of oxygen content in GDP ablator On this side I multiplied lateral variations x100 just to show what I am talking about With lateral modulations x100 for illustrative purpose S. W. Haan, H. Huang, M. A. Johnson, M. Stadermann, S. Baxamusa, S. Bhandarkar, D. S. Clark, V. Smalyuk, and H. F. Robey, Instability growth seeded by oxygen in CH shells on the National Ignition Facility, Physics of Plasmas 22, 032708 (2015) There is a variety of data from target fab suggesting transverse inhomogeneity; if those modulations are variations in oxygen near the outer surface, then simulations say they seed late-time perturbations ~2-3x bigger than from surface roughness. 3D HGR experiments show structure that would be very mysterious without “oxygen hypothesis” For high-foot implosions, the growth is low (reduction similar to surface roughness growth) For upcoming “adiabat shaping” implosions, the growth is also low 11 Growth from oxygen is ~3x bigger than from surface ripples or equivalent density modulations Oxygen in GDP increases its density according to Δρ= 0.029*at% I can normalize to “equivalent ρR modulation” using this density increase 8000 Growth factor in ρR Oxygen modulation with e-d/30 ramp from outside 6000 Oxygen only (same amount of O as equivalent ρR) i.e. define RG(t)= ρR(rms) ρR(avg) 4000 and plot 2000 RG(Peak Vel) RG(0) 0 0 Equivalent density modulation Oxygen-only launches a velocity deviation, shock is stronger where oxygen is smaller. 2/3 of oxygen impact is Outer surface ripple from this, and 1/3 50 100 150 200 from the density increase Mode number 12 Oxygen seeds the most growth when the modulation is in the outer few µm Simulations in which oxygen modulations, or density modulations, are placed at various depths in the shell. Plotted is relative growth in ρR(rms), mode 60, at time of peak velocity. Normalize to same initial ρR. 5 Relative growth of mode 60 Depth Seed with oxygen and density 4 Oxygen and density with e-d/30 ramp 3 2 Surface ripple Density alone 1 0 -200 -150 -100 -50 0 Depth in shell where oxygen (and/or density) are modulated (µm) 13 Oxygen seeds the most growth when the modulation is in the outer few µm Simulations in which oxygen modulations, or density modulations, are placed at various depths in the shell. Plotted is relative growth in ρR(rms), mode 60, at time of peak velocity. Normalize to same initial ρR. 5 Relative growth of mode 60 For oxygen near outer surface, where this is ~3, the best measure is Oxygen * depth (ppm-µm) and we care about Seed with oxygen and density 4 Oxygen and density with e-d/30 ramp 3 2 0.03 at% * 30µm = 1 at%-µm at 100 µm lateral scale Surface ripple Density alone 1 (equivalent to 100nm roughness) 0 -200 -150 -100 -50 0 Depth in shell where oxygen (and/or density) are modulated (µm) 14 Why should the oxygen have lateral variations? 2±0.005 at% ~2 at% 1 at% 30µm radial scale length Oxygen in GDP. Lateral variations “immeasurably small,” too small to see in a plot like this. 0.01%? Snapshot of oxygen content in GDP ablator On this side I multiplied lateral variations x100 just to show what I am talking about With lateral modulations x100 for illustrative purpose Many peoples’ intuition is that the oxygen should be uniform, because the processes that cause it seem uniform. However: § The composition is almost immeausurably uniform, modulations would be <1% of the oxygen that we know is there § The contour levels we are considering are smooth to 10s of nm. What does “uniform” even mean if surface roughness and contour levels are similar? Processes that lead to surface roughness could lead to O variation too. § The polymer is a blend of complex molecules, with various bonds that O can find “free radicals” i.e. C with less than 4 bonds) § We know exposure to x-rays and UV changes the affinity for O The burden of proof needs to be on those who say it’s too uniform to matter. Why should the oxygen be uniform to <0.002 at%? 15 Exposure to x-rays, UV, or visible is known to “paint” oxygen into the CH Experiment done by Kevin Sequoia , GA, four years ago PR X-ray beam, narrowed to ~20°! 5-10keV x-rays rotation! First expose the shell to a band of the PR x-rays K. L. Sequoia, H. Huang, R. B. Stephens, K. A. Moreno, K. C. Chen, and A. Nikroo, Fusion Sci. Technol. 59, 35 (2011). 16 Exposure to x-rays, UV, or visible is known to “paint” oxygen into the CH Experiment done by Kevin Sequoia , GA, four years ago 1 mm (16 rows) X-ray beam! 5-10keV x-rays 16 detectors! rotation! Then rotate it and use the usual PR setup to diagnose it K. L. Sequoia, H. Huang, R. B. Stephens, K. A. Moreno, K. C. Chen, and A. Nikroo, Fusion Sci. Technol. 59, 35 (2011). 17 Exposure to x-rays, UV, or visible is known to “paint” oxygen into the CH Experiment done by Kevin Sequoia , GA, four years ago 1 mm (16 rows) X-ray beam! 5-10keV x-rays 16 detectors! This increased PR absorption, equivalent to deposition of 0.2 at% of O in the exposed band (uniform in radius). rotation! Then rotate it and use the usual PR setup to diagnose it Similar process occurs from UV and optical exposure. More recent work by Sal Baxamusa has identified three processes by which O is attached into GDP: Ø H2O is absorbed from ambient (the 3at%-30µm outer layer & 0.5 at% bulk) Ø High photon energies (x-rays, hard UV) create additional sites into which H2O bonds Ø Lower photon energies (soft UV, light) induce absorption of O2, which otherwise diffuses around unattached within the porous GDP K. L. Sequoia, H. Huang, R. B. Stephens, K. A. Moreno, K. C. Chen, and A. Nikroo, Fusion Sci. Technol. 59, 35 (2011). 18 Slide from Sal Baxamusa Unlike most plastics, even low-energy photons cause GDP to photo-oxidize 0.3 Δ O (at%) = 9.5*A OH/CH 0.25 0.2 Hg arc lamp 365 nm LED 405 nm LED 445 nm LED 532 nm LED 0.15 0.1 0.05 4Pi optical characterization, blue LED, penetration ~5µm 0 -0.05 2 10 2-3 weeks of typical room light Fill tube UV glue cure, new protocol* 3 4 10 10 2 Exposure dose (mJ/cm ) 5 *Prior to Aug 2014, 10 UV exposure was several X higher, caused slumping in N140819 Generating reliable dose-response curves is an ongoing activity Routine “non-destructive” capsule characterization is estimated to cause about 0.1 at% photoabsorbed oxygen Sal’s estimated typical additional oxidation due to 4pi blue LED Penetrates ~5µm (~1/6 of our test case) High-O regions are where diagnostic goes back for closer look at interesting areas Ablation front deformation at peak velocity 0.1 at% 2.5µm 0.03 at% -1.2µm This routine characterization step does NOT look like an important source of oxygen nonuniformity 20 Target characterization has given us a lot of information about O in GDP, but not enough yet GDP has oxygen, mostly in the outer ~20µm, ramping from bulk ~0.5 at% up to 2-5 at% at surface Oxygen comes in mostly as H2O; molecular O2 diffuses more freely in shell. Absorption does happen, often photon-assisted Oxygen in GDP increases its density by 0.029 g/cc/at%. Corresponds to just fitting in without changing CH structure. Amount of O depends on history, light/UV exposure, and on the density of available bonds in the GDP Transverse variability of something internal is indicated by “PSDI through the shell” (Mike Johnson) and consistent with Precision Radiography data (Haibo Huang) Something like “2±0.01 at% O in outer 30µm” is consistent with everything we know, suggested by “PSDI through the shell,” and causes perturbations about 2x those caused by the surface spec 21 3D Rayleigh-Taylor experiments are a great test of whether there is something like this going on Experiments by Vladimir Smalyuk,1 Dan Casey, design Steve Weber. Goal: image the modulations in single-pass transmission for “native roughness” GDP. Previous experiments (Kumar Raman et al.) with preimposed surface ripples had confirmed our ability to calculate growth fairly well As we went into these last fall, the “oxygen-dominant hypothesis” predicted that we would see larger perturbations than expected from surface roughness alone. (For previous experiments with large preimposed single-mode ripples, the big ripples dominate, but as we go to smoother surfaces, the oxygen starts to dominate.) 1V.A. Smalyuk, S.V. Weber, D.T. Casey, D.S. Clark, J.E. Field, S.W. Haan, A.V. Hamza, D.E. Hoover, O.L. Landen, A. Nikroo, H.F. Robey and C.R. Weber (2015). Hydrodynamic instability experiments with three-dimensional modulations at the National Ignition Facility. High Power Laser Science and Engineering, 3, e17 doi:10.1017/hpl.2015.12 22 Steve Weber calculated what it should look like, from the surface roughness Experiments had pre-imposed divots, 2nd and 3rd had tents Divots 3D simulation with blurring of 3rd shot (Steve Weber) Accidental feature 23 The 3D Rayleigh-Taylor experiments would be utterly mysterious if we hadn’t thought about oxygen seeding Experiments had pre-imposed divots, 2nd and 3rd had tents On 3rd shot, we eliminated much of the UV irradiation. Happened to have a surface feature right in the field of view. The first two shots showed features that could have 3D been caused by UV during simulation assembly. So far we do with blurring NOT have a detailed of 3rd shot scenario to explain this. (Steve Preimposed divots First shot: “the ring” and overall roughness more than expected Weber) Tent Second shot: “the eye” and overall roughness more than expected Accidental feature Experiment. Feature more pronounced than expected (associated oxygen?). Other perturbations also bigger. 400 µm 24 High-foot and “adiabat shaped” implosions are less sensitive to the oxygen-seeded perturbation growth The usual growth factor to peak velocity of conventional surface perturbations Seeded with oxygen, amplitude at peak velocity / equivalent initial ρR modulation 2500 Low-foot Low-foot “Adiabat shaping” with reoptimized peak 800 600 “Adiabat shaping” pulse 400 200 High-foot 0 -200 0 50 100 Mode number 150 200 Growth factor to ablation front Growth factor to ablation front 1000 “Adiabat shaping” with reoptimized peak 2000 “Adiabat shaping” pulse 1500 1000 500 High-foot 0 0 50 100 150 200 Mode number • Generally, O-seeded growth is ~2-3x bigger than from surface ripples with same ρR • High-foot growth is 2-3x less than low-foot, for either seed, except at lowest modes • “Adiabat shaping” pulse is also less sensitive to oxygen modulations, albeit not quite as much so as the high-foot implosions, and depends on details 25 There is a somewhat mature campaign using HDC capsules There are several ignition designs that differ in hohlraum details, pulse shape. Capsules differ only in the thickness of the doped layer. Many current experiments use undoped shells. 1110 µm Planning assumes surface roughness based on high-def AFM, which is ~3x rougher than we used to expect for HDC HDC 3.476 g/cc 76 µm thick 0.275 at% W 20 µm thick (for 3-step design) DT 0.255 g/cc 55.6 µm thick Outer surface is wellcharacterized and wellreported. Inner surface and bulk homogeneity might still have issues.1 1W. Recent capsules have nano-crystalline outer coating and look similar to the “old HDC” curve! Requieron, yesterday 26 The Be program is just getting underway, under LANL leadership 1050 µm Be+Cu (Total thickness 160 µm) 925 920 900 895 890 DT ice (70 µm) DT gas 0% 0.4% 1.0% 0.4% 0% This is the design currently being tested 6 shots so far (3 keyholes, 1 symcap, 2 ConAs). First DT layer last week, results too late for slides. Still sorting out hohlraum symmetry, details of pulse shaping. All results so far are very positive, and we are excited about the prospects with Be J.L. Kline, D.C. Wilson, A.N. Simakov, and A. Yi Andrei N. Simakov, Douglas C. Wilson, Sunghwan A. Yi, John L. Kline, Daniel S. Clark, Jose L. Milovich, Jay D. Salmonson and Steven H. Batha, Optimized beryllium target design for indirectly driven inertial confinement fusion experiments on the National Ignition Facility, Phys. Plasmas 21, 022701 (2014) 27 Be fabrication issues are still being explored What we are making is good for current experiments, but there are issues ahead: Coating process is inclined to make defects (voids, few µm x 100nm, and “nodules” with ~2% density defect) Irregular Cu diffusion1 seems to be under control via oxide layers,2 but diffusion and/ or layer irregularities could still be unacceptable We are still iterating on final surface roughness requirements Coating includes Ar and O, we need to ensure that homogeneity is acceptable 1Huang et al. Fusion Sci. Technol. 63, 190 (2013) et al. Fusion Sci. Technol. 63, 208 (2013) 2Youngblood 28 Summary/Outline We are making good progress toward ignition, and target fabrication is a vital ingredient For the three shotsprogress we have considered in detail, simulations show rough agreement with the data but not a perfect match This 3D simulation by Dan Clark of shot N120321 nicely shows the issues keV N120321 t = 22.85 ns (bang time) g/cm3 4.0 500.0 3.0 375.0 2.0 250.0 1.0 125.0 0.0 0.0 fuel-ablator interface fill tube defect tent defect LawrenceImploded Livermore National Laboratory shape at bang time Green surface = fuel-ablator interface Temperature on left, density on right We are incorporating our most upTent understanding feature is 2-3x bigger to-date of the role than we 1-2 years ago ofrealized the tent, hohlraum drive asymmetries, and other perturbation sources into 2-D and Global out-of-round from 3-D simulationsasymmetry of NIF implosions hohlraum While we do not match all of the Shorter wavelength irregularities data within the error bars, there is are agreement probably for bigger than rough both low andshown, high foot shots, and heavily because of “clean” oxygen nonuniformity mixed shots in GDP The precise effects of the tent and The program is working to hohlraum asymmetries are minimize these drivers features and their probably the biggest for the remaining growthdiscrepancies and impactand subjects for continuing work Developing other options is also important: High Density Carbon, Be, other hohlraum designs 6 29