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Tripled Yield in Direct-Drive Laser Fusion Through Statistical Modelling V ARTICLE https://doi.org/10.1038/s41586-019-0877-0 Tripled yield in direct-drive laser fusion through statistical modelling V. Gopalaswamy1,2*, R. Betti1,2,3, J. P. Knauer1, N. Luciani1,2,4, D. Patel1,2, K. M. Woo1,3, A. Bose1,5, I. V. Igumenshchev1, E. M. Campbell1, K. S. Anderson1, K. A. Bauer1, M. J. Bonino1, D. Cao1, A. R. Christopherson1,2, G. W. Collins1, T. J. B. Collins1, J. R. Davies1, J. A. Delettrez1, D. H. Edgell1, R. Epstein1, C. J. Forrest1, D. H. Froula1, V. Y. Glebov1, V. N. Goncharov1, D. R. Harding1, S. X. Hu1, D. W. Jacobs-Perkins1, R. T. Janezic1, J. H. Kelly1, O. M. Mannion1,3, A. Maximov1,2, F. J. Marshall1, D. T. Michel1, S. Miller1,2, S. F. B. Morse1, J. Palastro1, J. Peebles1, P. B. Radha1, S. P. Regan1, S. Sampat1, T. C. Sangster1, A. B. Sefkow1, W. Seka1, R. C. Shah1, W. T. Shmyada1, A. Shvydky1, C. Stoeckl1, A. A. Solodov1, W. Theobald1, J. D. Zuegel1, M. Gatu Johnson5, R. D. Petrasso5, C. K. Li5 & J. A. Frenje5 Focusing laser light onto a very small target can produce the conditions for laboratory-scale nuclear fusion of hydrogen isotopes. The lack of accurate predictive models, which are essential for the design of high-performance laser-fusion experiments, is a major obstacle to achieving thermonuclear ignition. Here we report a statistical approach that was used to design and quantitatively predict the results of implosions of solid deuterium–tritium targets carried out with the 30-kilojoule OMEGA laser system, leading to tripling of the fusion yield to its highest value so far for direct-drive laser fusion. When scaled to the laser energies of the National Ignition Facility (1.9 megajoules), these targets are predicted to produce a fusion energy output of about 500 kilojoules—several times larger than the fusion yields currently achieved at that facility. This approach could guide the exploration of the vast parameter space of thermonuclear ignition conditions and enhance our understanding of laser-fusion physics. Inertial confinement fusion (ICF)1–3 uses drivers such as lasers or where energy deposition by α particles is the dominant heating mech- pulsed power to implode a millimetre-size capsule made of a layer anism in the fusing plasma. Obtaining a burning plasma is considered of cryogenic deuterium (D) and tritium (T) enclosed within an abla- to be an important intermediate milestone on the path to ignition. tor shell composed of low-atomic-number material (typically a CH Recent publications provide detailed summaries of the indirect-17,18 polymer, high-density carbon or beryllium). The implosion produces and direct-drive19 efforts to achieve ignition, as well as an overview of copious amounts of DT fusion reactions, each producing a 14.1-MeV the current status of ICF13. neutron and a 3.5-MeV α particle. Laser ICF uses either direct illu- Historically, the design of ICF implosions has been primarily driven by mination of the capsule (direct drive)4 or indirect illumination of the one-dimensional (1D) and two-dimensional radiation–hydrodynamic capsule via X-rays produced by laser heating of a high-atomic-number (RH) codes20–24. Because of the substantial computational burden metal enclosure called a hohlraum (indirect drive)5. In direct-drive imposed by well resolved three-dimensional (3D) simulations, the laser fusion, laser light directly incident on the capsule surface at inten- use of 3D codes is mostly limited to post-shot simulations25,26. These sities of I ≈ 1015 W cm−2 drives mass ablation, which accelerates the simulations often include degradation sources (such as the ablator– shell inwards at velocities from 300 to 500 km s−1. As the shell con- fuel mix), engineering features (the stalk, fill tube or tent holding the verges, the central pressure increases and slows down the imploding capsule) and offsets from the target chamber centre to match experi- capsule. The central core reaches temperatures of several kiloelectron- mental observables post hoc, but cannot yet reliably predict the results volts, and the heat flux from the centre ablates fuel off the inner shell of a future experiment when changes to the target specifications and surface to form a low-density (30–100 g cm−3) central hot spot. This laser pulse shapes are made. At the Laboratory for Laser Energetics, the hot spot is confined by a nearly Fermi-degenerate6 (200–1,000 g cm−3) 1D RH code LILAC23 is used to design direct-drive implosions, with shell over a subnanosecond confinement time during which fusion experimentally benchmarked physics models for cross-beam energy reactions occur. If the areal density (ρR) of the compressed core is transfer27,28, thermal transport28,29 and first-principles models of the high enough, the α particles deposit their energy within the hot core, equation of state30. In part because of these improvements in com- driving a feedback process (known as alpha heating7–9) that amplifies puter modelling, experiments carried out with the OMEGA laser31 at the fusion reaction rates. Under the appropriate conditions of pres- energies of 26–28 kJ have demonstrated core compression that would sure, temperature and confinement time10–12, the alpha-heating process produce substantial fusion α-particle self-heating when scaled hydro- becomes intense enough to ‘ignite’ the central hot spot, resulting in dynamically to NIF energies (1.9 MJ)32,33 . Considerable performance a thermonuclear burn wave propagating radially through the entire improvements have also been achieved in indirect-drive ICF, with dense fuel, producing fusion energy yields many times greater than recent implosions of DT-layered targets producing over 50 kJ of fusion the driver energy input. Until now, demonstrating ignition via laser yield (about 2 × 1016 fusion reactions)14, greatly exceeding the energy fusion has been an elusive goal of the United States’ ICF Program13, input to the fusion fuel. although recent experiments14,15 using indirect drive at the National Despite the remarkable progress in modelling, it is still not possible to Ignition Facility (NIF)16 are approaching burning-plasma conditions7,8, predict a priori the results of an ICF experiment with enough accuracy 1Laboratory for Laser Energetics, University of Rochester, Rochester, NY, USA. 2Department of Mechanical Engineering, University of Rochester, Rochester, NY, USA. 3Department of Physics and Astronomy, University of Rochester, Rochester, NY, USA. 4Dipartimento di Energetica, Politecnico di Milano, Milan, Italy. 5Massachusetts Institute of Technology, Cambridge, MA, USA. *e-mail: [email protected] 31 JANUARY 2019 | VOL 565 | NATURE | 581 © 2019 Springer Nature Limited. All rights reserved. RESEARCH ARTICLE a Shot 80802 the DT ice34, or the ramp of the laser to full power, which is designed Ablator to adiabatically compress the shell. The late portion of the laser pulse 8.0 μm Ice 80802 can also be varied to prevent coasting of the shell or to launch a late 25 35 53 μm shock as in shock ignition . 20 The unexplored parameter space of the laser pulse shape and target specifications is vast, and today’s RH codes are not accurate enough to 15 Gas enable a high-confidence design of the optimum implosion that can 10 be applied at the existing ICF laser facilities. In addition, the param- 379 μm Power (TW) 5 eter space can be further extended if minor upgrades to the facility are included, such as changing the laser spot size on the target, the 0 target mount or the DT filling procedure19. It is not clear at this time 012 whether the lack of predictive capability in the RH codes is a result of Time (ns) inaccuracies in the physics models or of incomplete inputs provided b Shot 87266 to the codes or, as is most likely, both. It is clear, however, that the lack Ablator of predictive capability has hindered progress in improving the fusion yields in ICF. It is also clear that in this vast and unexplored parameter 7.4 μm 87266 Ice 25 space, there almost certainly exists a combination of target specifica- 42 μm tions, laser pulse shape and minor upgrades that leads to considerably 20 better performance than today’s implosions. 15 Here, we describe a new, statistically driven framework to aid in the Gas 10 traversal of this space, predict and design high-performance implo- Power (TW) sions and speed up the quest for thermonuclear ignition. The funda- 440 μm 5 mental principle behind this new framework is that even though the exp 0 RH codes are inaccurate, the experimental observables O are sim 012 expected to be correlated to the code output variables O because both the experiment and the code use the same input—that is, the laser Time (ns) pulse shape and the target geometry. Because the codes do not accurately reproduce the experimental results, the code–experiment expsim Fig. 1 | Target and laser pulse shape in the first phase of the relations are no longer one to one for each variable (Ojj≠ O ); Optimization Campaign. a, b, Shots 80802 (a) and 87266 (b) were the instead, a more global relation is theorized to exist, for which each first and last shot, respectively, of the first phase of the Optimization experimental observable is correlated to a combination of code output Campaign. The implosion design was guided by statistical methods and variables. led to the highest yield for direct-drive ICF. Design changes included To elucidate this approach, we use a set of parameters I1D to denote larger target radii, reductions of the DT ice thickness (reflected in the the initial conditions determining the 1D implosion dynamics (that is, changes to the gas, ice and ablator layer thicknesses shown on the left) and the laser pulse shape and target specifications) and S for the 3D non- substantial changes to the laser pulse shape.
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