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Recent results from experiments and simulation [1], [2] of magnetically driven pulsed power liners have explored the role of the early-time electrothermal instability in the evolution of the magneto-Rayleigh-Taylor instability. Our focus will be on understanding the development of such instabilities and the potential stabilization mechanisms, which we expect could play a significant role in supporting the success of the MagLIF (Magnetized Liner Inertial Fusion) program. MagLIF is a particularly promising emerging concept for producing fusion energy in amounts greater than breakeven. Better understanding of magnetoRayleigh-Taylor instabilities through advanced modeling will improve the MagLIF concept. Experiments have shown that studies of high-energy density plasmas from wire-array implosions require physics modeling that goes well beyond simple models such as ideal magnetohydrodynamics. The goal of this work is to provide increased understanding of these experiments by employing simulations with a multifluid extended-MHD model, which uses kinetic closures for thermal conductivity, resistivity, and viscosity. We will use codes easily available to the wider research community, including university students, with a secondary goal of providing the community with well-benchmarked tools capable of advanced modeling of high-energy-density plasmas. This proposal also pioneers a hybrid fluid-kinetic modeling approach that is applicable to other high-energydensity physics scenarios.

Magnetized Liner Inertial Fusion is a magneto-inertial fusion concept in which a metal cylindrical shell containing deuterium gas is axially magnetized, the fuel is heated with a laser, and the metal cylinder is imploded by the current of the Z Machine. In previous experiments, the axial magnetic field was 9-10 T, the laser energy absorbed in the fuel was less than 1 kJ, and the peak current flowing through the target was about 17 MA. These experiments produced fusion-relevant temperatures and densities at stagnation, up to 3e12 primary DD neutrons, and a magnetic field in the fuel sufficient to trap a sizable fraction of the fusion-produced tritons.

Magnetized Liner Inertial Fusion (MagLIF) has provided many promising results including initial DD neutron yields of >1012 [1] and high magnetization in the stagnated column (BR>105 G cm) [2]. An interesting result from initial experiments was the presence of a quasi-helical structure to the stagnation column, which is postulated to be the result of feedthrough from a helical structure observed on the outside of pre-magnetized liners [3]. We present the first data exploring the connection of the stagnation morphology to these early-time structures by varying the initial liner conditions in two ways. We studied feedthrough of the instabilities by varying the liner aspect ratio (radius/thickness) and demonstrated that lower aspect ratio liners (i.e. thicker liners) exhibited less feedthrough of the instabilities, and that the opposite was true for higher aspect ratio liners. We then explored the role of the seed for these instabilities by adding a coating to the outer surface of these high aspect ratio liners, a technique which has previously been shown to minimize Electro-Thermal Instabilities which seed other instabilities. Data showed that, using these coatings, we could produce a cylindrical stagnation column with promising neutron yields. We will discuss the differences in stagnation in the different cases, including inferred differences in the liner density, the stagnation morphology, magnetization and the plasma conditions.

The Nernst effect plays the dominant role in the subsonic transport of magnetic flux in magnetized high-energy-density (HED) plasmas, where the plasma beta is high and the temperature diffusivity is much greater than the magnetic diffusivity. This parameter range is characteristic of the Magnetized Liner Inertial Fusion and other magnetoinertial fusion approaches near stagnation. It is demonstrated that the transport of magnetic flux in HED plasmas proceeds via the Nernst thermomagnetic waves propagating at the local Nernst velocity with respect to the plasma particles down the temperature gradient. The plasma resistivity strongly damps their propagation in the opposite direction. The Nernst waves, which had been theoretically predicted in the 1960s and observed in metals at cryogenic temperatures, have never been discussed for strongly driven, highly inhomogeneous, magnetized HED plasmas at kilo-electron-volt temperatures. Semianalytical, self-similar solutions are developed for the plasma transport equations at constant pressure involving the Nernst waves. The effect of the Nernst waves on the losses of heat and magnetic flux from magnetically insulated hot plasmas is discussed. The results from finite difference MHD simulations with particular numerical techniques are compared with the self-similar solutions. Finally, the constraint of constant pressure is removed and the simulations show that the self-similar profiles are asymptotically reproduced in a region between outgoing pressure disturbances. The self-similar solutions and finite difference simulations provide a challenging verification test for MHD codes that include the Nernst effect.

Magnetic implosion of cylindrical metallic shells (liners) is an effective method for compressing preheated, premagnetized fusion fuel to thermonuclear conditions [M. R. Gomez et al., Phys. Rev. Lett. 113, 155003 (2014)] but suffers from magneto-Rayleigh–Taylor instabilities (MRTI) that limit the attainable fuel pressure, density, and temperature. A novel method proposed by Schmit et al. [Phys. Rev. Lett. 117, 205001 (2016)] uses a helical magnetic drive field with a dynamic polarization at the outer surface of the liner during implosion, reducing (linear) MRTI growth by one to two orders of magnitude via a solid liner dynamic screw pinch (SLDSP) effect. Our work explores the design features necessary for successful experimental implementation of this concept. Whereas typical experiments employ purely azimuthal drive fields to implode initially solid liners, SLDSP experiments establish a helical drive field at the liner outer surface, resulting in enhanced average magnetic pressure per unit drive current, mild spatial nonuniformities in the magnetic drive pressure, and augmented static initial inductance in the pulsed-power drive circuit. Each of these topics has been addressed using transient magnetic and magnetohydrodynamic simulations; the results have led to a credible design space for SLDSP experiments on the Z Facility. We qualitatively assess the stabilizing effects of the SLDSP mechanism by comparing MRTI growth in a liner implosion simulation driven by an azimuthal magnetic field vs one driven with a helical magnetic field; the results indicate an apparent reduction in MRTI growth when a helical drive field is employed.

A multi-frame shadowgraphy diagnostic has been developed and applied to laser preheat experiments relevant to the Magnetized Liner Inertial Fusion (MagLIF) concept. The diagnostic views the plasma created by laser preheat in MagLIF-relevant gas cells immediately after the laser deposits energy as well as the resulting blast wave evolution later in time. The expansion of the blast wave is modeled with 1D radiation-hydrodynamic simulations that relate the boundary of the blast wave at a given time to the energy deposited into the fuel. This technique is applied to four different preheat protocols that have been used in integrated MagLIF experiments to infer the amount of energy deposited by the laser into the fuel. The results of the integrated MagLIF experiments are compared with those of two-dimensional LASNEX simulations. The best performing shots returned neutron yields ∼40–55% of the simulated predictions for three different preheat protocols.

The Magnetized Liner Inertial Fusion (MagLIF) concept involves the compression of a magnetized fuel such that the stagnated fuel contains a magnetic field that can suppress heat flow losses and confine α particles. Magnetic confinement of α particles reduces the fuel ρR required for ignition. Recent work [1,2] has demonstrated that the magnitude of the magnetic field in deuterium fuel can be inferred from the yields and spectra of secondary DT neutrons. In this work we investigate the potential for using the shape of the secondary neutron spectra to diagnose the magnetic field topology in the stagnated fuel. Three different field topologies that could possibly occur in MagLIF experiments are studied: (1) a cylindrical fuel column containing axial and azimuthal magnetic field components, (2) a fuel column which is pinched at the ends to form a magnetic mirror and (3) a fuel column that has a helical tube shape with magnetic field lines following the helical path of the tube’s axis. Each topology is motivated by observations from experimental or simulated MagLIF data. For each topology we use a multi-physics model to investigate the shapes of the secondary neutron spectra emitted from a steady-state stagnated fuel column. It is found that the azimuthal and helical topologies are more suitable than the mirror topology for reproducing an asymmetry in the axial spectra that was observed in experiments. Gorgon MHD simulations of the MagLIF implosion in 1D are also carried out. These show that sufficient azimuthal magnetic field can penetrate from the liner into the fuel to qualitatively reproduce the observed spectral asymmetry.

We report experimental results and simulations showing efficient laser energy coupling into plasmas at conditions relevant to the magnetized liner inertial fusion (MagLIF) concept. In MagLIF, to limit convergence and increase the hydrodynamic stability of the implosion, the fuel must be efficiently preheated. To determine the efficiency and physics of preheating by a laser, an Ar plasma with n_{e}/n_{crit}∼0.04 is irradiated by a multi-ns, multi-kJ, 0.35-μm, phase-plate-smoothed laser at spot-averaged intensities ranging from 1.0×10^{14} to 2.5×10^{14}W/cm^{2} and pulse widths from 2 to 10 ns. Time-resolved x-ray images of the laser-heated plasma are compared to two-dimensional radiation-hydrodynamic simulations that show agreement with the propagating emission front, a comparison that constrains laser energy deposition to the plasma. The experiments show that long-pulse, modest-intensity (I=1.5×10^{14}W/cm^{2}) beams can efficiently couple energy (∼82% of the incident energy) to MagLIF-relevant long-length (9.5 mm) underdense plasmas. The demonstrated heating efficiency is significantly higher than is thought to have been achieved in early integrated MagLIF experiments [A. B. Sefkow et al., Phys. Plasmas 21, 072711 (2014)10.1063/1.4890298].

The magnetized liner inertial fusion (MagLIF) approach to inertial confinement fusion [1] involves subsonic/isobaric compression and heating of a deuterium-tritium plasma with frozen-in magnetic flux by a heavy cylindrical liner. In order to understand the transport of magnetic flux, a recent paper [2] developed self-similar solutions in one dimension for the loss of heat and magnetic flux from a semi-infinite planar medium of high plasma beta and constant pressure to a liner wall due to diffusion and advection. The resistive diffusion included the Nernst effect based on the classical Branginskii plasma transport terms. These solutions were compared against a one dimensional Lagrangian code that also included the Ettingshausen effect in the thermal diffusion. The present work generalizes the results of [2] in two ways. First, we demonstrate new exact self-similar solutions obtained for a planar geometry and suitable for code verification, such as magnetic reconnection. Second, we use our Lagrangian code to address a similar problem of heat and flux loss in a transverse magnetic field but for a deuterium plasma bounded by a cylindrical liner of finite radius. In a finite volume the plasma may stay isobaric, but the pressure cannot remain constant in time because of heat losses to the liner. Consequently, exact self-similar solutions are not possible, and the above mentioned numerical code, verified in [2], is extended to cylindrical geometry. We will investigate the case with large electron Hall parameter and large plasma beta to determine if the effective diffusion coefficients for heat and magnetic flux losses decrease inversely with the first power of the Hall parameter, as in the planar case and in Bohm diffusion, or more strongly.

Magnetized Liner Inertial Fusion (MagLIF, [1]) is an inertial confinement fusion concept that includes a strong magnetic field embedded in the fuel to mitigate thermal conduction loss during the implosion. Magnetization of the target in MagLIF experiments on Sandia's 20 MA Z Machine has traditionally required an external pair of field coils in a Helmholtz-like configuration [2]. The novel AutoMag concept employs a composite liner (cylindrical tube) with helically oriented conduction paths separated by insulating material to provide both axial premagnetization of the fuel (during a slow rising current pre-pulse) and fuel compression (during a fast rising main current pulse). This integrated axial field production mechanism offers a few potential advantages when compared to the external field coils currently being used on Z. AutoMag seeks to increase drive current for MagLIF experiments by decreasing the transmission line inductance, provide higher peak axial field levels (>30 T) inside of the liner without compromising diagnostic access, and offer new mirrored magnetic field topologies within the fuel column. 3D electromagnetic simulations using ANSYS Maxwell have been completed in order to explore the current distributions within the helical conduction paths, the inter-wire dielectric strength properties, and the thermal properties of the helical conduction paths during a nominal premagnetization phase (∼1 MA in 100ns). Initial designs show a broad range of peak Bz from 20 T to 100T in single helix configurations before breakdown field levels in the dielectric become a concern due to increasing aggressiveness of the helical pitch. Stacked helix designs show capability to provide mirror field topologies with peak Bz near the top and bottom of the liner and mirror ratios (Bzmax/Bzmin) approaching 1.5. These designs will soon be tested in experiments (∼1 MA, 100ns) seeking to measure Bz(t) inside of the liner and assess failure mechanisms. Simulations of implosion dynamics for several AutoMag liner designs have been completed using the 3D MHD code Gorgon [3] to evaluate the effects of conductor/insulator material choice and the quality of implosion symmetry for this concept.

The ICF design code HYDRA has been used to model Magnetized liner inertial fusion (MagLIF) experiments1 and NIF2 and Omega3 hohlraums with imposed magnetic fields. The current MHD package in HYDRA includes a resistive MHD solver, the dielectric pressure source term, anisotropic electron thermal conduction and magnetic field effects on alpha charged particle transport. We describe the addition of terms in the MHD package and their effect on representative simulations of interest to experimentalists.

The dynamics of Magnetized Liner Inertial Fusion (MagLIF)1, a new and promising approach to pulsed power fusion, are presently under detailed study at Sandia National Laboratories. Alongside this, a comprehensive analysis of the influence of the specific liner design geometry in the MagLIF system on liner initiation is underway in the academic community.

Sandia National Laboratories is pursuing a variation of Magneto-Inertial Fusion called Magnetized Liner Inertial Fusion, or MagLIF. The MagLIF approach requires magnetization of the deuterium fuel, which is accomplished by an initial external B-Field and laser-driven pre-heat. While magnetization is crucial to the concept, it is challenging to couple sufficient energy to the fuel, since laser-plasma instabilities exist, and a compromise between laser spot size, laser entrance window thickness, and fuel density must be found. Nonlinear processes in laser plasma interaction, or laser-plasma instabilities (LPI), complicate the deposition of laser energy by enhanced absorption, backscatter, filamentation and beam-spray. Key LPI processes are determined, and mitigation methods are discussed. Results with and without improvement measures are presented.

High current pulsed-power generators efficiently store and deliver magnetic energy to z-pinch targets. We review applications of magnetically driven implosions (MDIs) to inertial confinement fusion. Previous research on MDIs of wire-array z-pinches for radiation-driven indirect-drive target designs is summarized. Indirect-drive designs are compared with new targets that are imploded by direct application of magnetic pressure produced by the pulsed-power current pulse. We describe target design elements such as larger absorbed energy, magnetized and pre-heated fuel, and cryogenic fuel layers that may relax fusion requirements. These elements are embodied in the magnetized liner inertial fusion (MagLIF) concept [Slutz “Pulsed-power-driven cylindrical liner implosions of laser pre-heated fuel magnetized with an axial field,” Phys. Plasmas, 17, 056303 (2010), and Stephen A. Slutz and Roger A. Vesey, “High-Gain Magnetized Inertial Fusion,” Phys. Rev. Lett., 108, 025003 (2012)]. MagLIF is in the class of magneto-inertial fusion targets. In MagLIF, the large drive currents produce an azimuthal magnetic field that compresses cylindrical liners containing pre-heated and axially pre-magnetized fusion fuel. Scientific breakeven may be achievable on the Z facility with this concept. Simulations of MagLIF with deuterium-tritium fuel indicate that the fusion energy yield can exceed the energy invested in heating the fuel at a peak drive current of about 27 MA. Scientific breakeven does not require alpha particle self-heating and is therefore not equivalent to ignition. Capabilities to perform these experiments will be developed on Z starting in 2013. These simulations and predictions must be validated against a series of experiments over the next five years. Near-term experiments are planned at drive currents of 16 MA with D2 fuel. MagLIF increases the efficiency of coupling energy (=target absorbed energy/driver stored energy) to targets by 10-150X relative to indirect-drive targets. MagLIF also increases the absolute energy absorbed by the target by 10-50X relative to indirect-drive targets. These increases could lead to higher fusion gains and yields. Single-shot high yields are of great utility to national security missions. Higher efficiency and higher gains may also translate into more compelling (lower cost and complexity) fusion reactor designs. We will discuss the broad goals of the emerging research on the MagLIF concept and identify some of the challenges. We will also summarize advances in pulsed-power technology and pulsed-power driver architectures that double the efficiency of the driver.

A technique to infer the areal density ρR of compressed deuterium (D) in cylindrical implosions from the ratio of secondary D–T (deuterium–tritium) neutrons to primary D–D neutrons is described and evaluated. For ρR to be proportional to the ratio of D–T to D–D yield, the increase in the D–T fusion cross-section with collisional slowing down of the tritium must be small, requiring ρR≪15T keV3/2 mg/cm2, where TkeV is the electron temperature in keV. The technique is applied to the results from laser-driven magnetized liner inertial fusion (MagLIF) targets on OMEGA, where ρR is certainly less than 4 mg/cm2. OMEGA MagLIF targets do not achieve a sufficiently high, radially integrated, axial magnetic field BR to confine the tritium, as occurs in Z MagLIF targets, because they are ∼10× smaller in radius. The inferred areal densities show that fuel convergence is reduced by preheating, by an applied axial magnetic field, and by increasing the initial fuel density, which are key features of the MagLIF scheme. The results are compared with 1-D and 2-D magnetohydrodynamic simulations for nominal laser and target parameters, which predict areal densities 2× to 3× higher than the measurements.A technique to infer the areal density ρR of compressed deuterium (D) in cylindrical implosions from the ratio of secondary D–T (deuterium–tritium) neutrons to primary D–D neutrons is described and evaluated. For ρR to be proportional to the ratio of D–T to D–D yield, the increase in the D–T fusion cross-section with collisional slowing down of the tritium must be small, requiring ρR≪15T keV3/2 mg/cm2, where TkeV is the electron temperature in keV. The technique is applied to the results from laser-driven magnetized liner inertial fusion (MagLIF) targets on OMEGA, where ρR is certainly less than 4 mg/cm2. OMEGA MagLIF targets do not achieve a sufficiently high, radially integrated, axial magnetic field BR to confine the tritium, as occurs in Z MagLIF targets, because they are ∼10× smaller in radius. The inferred areal densities show that fuel convergence is reduced by preheating, by an applied axial magnetic field, and by increasing the initial fuel density, which are key features of the MagLIF scheme. T...

In magneto-inertial-fusion experiments, energy losses such as a radiation need to be well controlled in order to maximize the compressional work done on the fuel and achieve thermonuclear conditions. One possible cause for high radiation losses is high-Z material mixing from the target components into the fuel. In this work, we analyze the effects of mix on target performance in Magnetized Liner Inertial Fusion (MagLIF) experiments at Sandia National Laboratories. Our results show that mix is likely produced from a variety of sources, approximately half of which originates during the laser heating phase and the remainder near stagnation, likely from the liner deceleration. By changing the “cushion” component of MagLIF targets from Al to Be, we achieved a 10× increase in neutron yield, a 60% increase in ion temperature, and an ∼50% increase in fuel energy at stagnation.

Laser-driven cylindrical implosions were conducted on the OMEGA laser as part of the laser-driven mini-MagLIF (Magnetized Liner Inertial Fusion) Campaign. Gated x-ray images were analyzed to infer shell trajectories and study the energy coupling in these implosions. Two-dimensional and three-dimensional HYDRA simulations were performed and post-processed to produce synthetic x-ray self-emission images for comparison. An analysis technique, which could be applied to both experimental and simulated x-ray images, was developed to characterize the shape and uniformity of the implosion. The analysis leads to a measurement of the average implosion velocity and axial implosion length, which can then be used to optimize the beam pointing and energy balance for future experiments. Discrepancies between simulation results and experiments allude to important physical processes that are not accounted for in the simulations. In 2-D simulations, the laser beam's azimuthal angle of incidence is not included because the ϕ-direction is not simulated, and thus, energy absorption is over-predicted. The 3-D simulation results are more consistent with the experiments, but the simulations do not include the calculation of cross-beam energy transfer or non-local thermal transport, which affects the energy coupled to the implosion. By appropriately adjusting the simulated energy balance and flux limit, the simulations can accurately model the experiments, which have achieved uniform implosions over a 700-μm-long region at velocities of approximately 200 km/s.Laser-driven cylindrical implosions were conducted on the OMEGA laser as part of the laser-driven mini-MagLIF (Magnetized Liner Inertial Fusion) Campaign. Gated x-ray images were analyzed to infer shell trajectories and study the energy coupling in these implosions. Two-dimensional and three-dimensional HYDRA simulations were performed and post-processed to produce synthetic x-ray self-emission images for comparison. An analysis technique, which could be applied to both experimental and simulated x-ray images, was developed to characterize the shape and uniformity of the implosion. The analysis leads to a measurement of the average implosion velocity and axial implosion length, which can then be used to optimize the beam pointing and energy balance for future experiments. Discrepancies between simulation results and experiments allude to important physical processes that are not accounted for in the simulations. In 2-D simulations, the laser beam's azimuthal angle of incidence is not included because the ...

A series of Magnetized Liner Inertial Fusion (MagLIF) experiments have been conducted in order to investigate the mix introduced from various target surfaces during the laser preheat stage. The material mixing was measured spectroscopically for a variety of preheat protocols by employing mid-atomic number surface coatings applied to different regions of the MagLIF target. The data show that the material from the top cushion region of the target can be mixed into the fuel during preheat. For some preheat protocols, our experiments show that the laser-entrance-hole (LEH) foil used to contain the fuel can be transported into the fuel a significant fraction of the stagnation length and degrade the target performance. Preheat protocols using pulse shapes of a few-ns duration result in the observable LEH foil mix both with and without phase-plate beam smoothing. In order to reduce this material mixing, a new capability was developed to allow for a low energy (∼20 J) laser pre-pulse to be delivered early in time (−20 ns) before the main laser pulse (∼1.5 kJ). In experiments, this preheat protocol showed no indications of the LEH foil mix. The experimental results are broadly in agreement with pre-shot two-dimensional HYDRA simulations that helped motivate the development of the early pre-pulse capability.

The Magnetized Liner Inertial Fusion concept (MagLIF) [Slutz et al., Phys. Plasmas 17, 056303 (2010)] is being studied on the Z facility at Sandia National Laboratories. Neutron yields greater than 1012 have been achieved with a drive current in the range of 17–18 MA and pure deuterium fuel [Gomez et al., Phys. Rev. Lett. 113, 155003 (2014)]. We show that 2D simulated yields are about twice the best yields obtained on Z and that a likely cause of this difference is the mix of material into the fuel. Mitigation strategies are presented. Previous numerical studies indicate that much larger yields (10–1000 MJ) should be possible with pulsed power machines producing larger drive currents (45–60 MA) than can be produced by the Z machine [Slutz et al., Phys. Plasmas 23, 022702 (2016)]. To test the accuracy of these 2D simulations, we present modifications to MagLIF experiments using the existing Z facility, for which 2D simulations predict a 100-fold enhancement of MagLIF fusion yields and considerable increases in burn temperatures. Experimental verification of these predictions would increase the credibility of predictions at higher drive currents.The Magnetized Liner Inertial Fusion concept (MagLIF) [Slutz et al., Phys. Plasmas 17, 056303 (2010)] is being studied on the Z facility at Sandia National Laboratories. Neutron yields greater than 1012 have been achieved with a drive current in the range of 17–18 MA and pure deuterium fuel [Gomez et al., Phys. Rev. Lett. 113, 155003 (2014)]. We show that 2D simulated yields are about twice the best yields obtained on Z and that a likely cause of this difference is the mix of material into the fuel. Mitigation strategies are presented. Previous numerical studies indicate that much larger yields (10–1000 MJ) should be possible with pulsed power machines producing larger drive currents (45–60 MA) than can be produced by the Z machine [Slutz et al., Phys. Plasmas 23, 022702 (2016)]. To test the accuracy of these 2D simulations, we present modifications to MagLIF experiments using the existing Z facility, for which 2D simulations predict a 100-fold enhancement of MagLIF fusion yields and considerable increase...

We recently developed a one-dimensional imager of neutrons on the Z facility. The instrument is designed for Magnetized Liner Inertial Fusion (MagLIF) experiments, which produce D-D neutrons yields of ∼3 × 1012. X-ray imaging indicates that the MagLIF stagnation region is a 10-mm long, ∼100-μm diameter column. The small radial extents and present yields precluded useful radial resolution, so a one-dimensional imager was developed. The imaging component is a 100-mm thick tungsten slit; a rolled-edge slit limits variations in the acceptance angle along the source. CR39 was chosen as a detector due to its negligible sensitivity to the bright x-ray environment in Z. A layer of high density poly-ethylene is used to enhance the sensitivity of CR39. We present data from fielding the instrument on Z, demonstrating reliable imaging and track densities consistent with diagnosed yields. For yields ∼3 × 1012, we obtain resolutions of ∼500 μm.

The Magnetized Liner Inertial Fusion (MagLIF) concept [Slutz et al. Phys. Plasmas 17, 056303 (2010); Gomez et al. Phys. Rev. Lett. 113, 155003 (2014)] is being studied on the Z facility at Sandia National Laboratories. MagLIF is a specific example of the more general Magnetized Inertial Fusion (MIF) approach to fusion. Numerical simulations indicate that yields approaching 100 kJ should be possible on the Z machine and much higher yields (10–1000 MJ) should be possible with pulsed power machines producing larger drive currents (45–60 MA) [Slutz et al. Phys. Plasmas 23, 022702 (2016)]. A significant advantage of MIF is that the implosions can be driven more slowly than conventional inertial fusion. In general, the efficiency of pulsed power machines increases with the current rise-time; however, we show by numerical simulation that the current and energy required to obtain a given fusion gain increase monotonically with the current rise-time over the range (10–500 ns). These results can be used to optimize the design of future accelerators to drive MIF concepts such as MagLIF. We also show that the required preheat energy increases strongly with current rise-time, which indicates that very long current rise-times are not desirable at least for MagLIF.

The MagLIF (Magnetized Liner Inertial Fusion) experiment at Sandia National Labs is one of the three main approaches to inertial confinement fusion. Radiographic measurements of the imploding liner have shown helical structuring that was not included in MagLIF scaling calculations but that could fundamentally change the viability of the approach. We present the first MagLIF linear dynamics simulations, using extended magnetohydrodynamical (XMHD) as well as standard MHD modeling, that reproduce these helical structures, thus enabling a physical understanding of their origin and development. Specifically, it is found that low-density plasma from the simulated power flow surfaces can compress the axial flux in the region surrounding the liner, leading to a strong layer of axial flux on the liner. The strong axial magnetic field on the liner imposes helical magneto-Rayleigh-Taylor perturbations into the imploding liner. A detailed comparison of XMHD and MHD modeling shows that there are defects in the MHD treatment of low-density plasma dynamics that are remedied by inclusion of the Hall term that is included in our XMHD model. In order to obtain fair agreement between XMHD and MHD, great care must be taken in the implementation of the numerics, especially for MHD. Even with a careful treatment of low-density plasma, MHD exhibits significant shortcomings that emphasize the importance of using XMHD modeling in pulsed-power driven high-energy-density experiments. The present results may explain why past MHD modeling efforts have failed to produce the helical structuring without initially imposing helical perturbations.

Laser-driven magnetized liner inertial fusion (MagLIF) is being developed on the OMEGA Laser System to study scaling. MagLIF targets require a preheat laser entrance window that can hold the gas in the target yet allow sufficient laser energy to enter the gas. For OMEGA MagLIF targets, 1.8-μm-thick polyimide foils were found to be sufficient to hold a fuel pressure of up to 14 atm. Transmission and reflection of an OMEGA beam incident on such foils were measured with a calorimeter and time-resolved spectrometers for 2.5-ns square-shaped pulses, with energies from 60 to 200 J, focused to intensities from 0.65 to 2.2 × 1014 W/cm2. The laser energy transmitted in every case exceeded that required to achieve the goal of preheating the gas to 100 eV. The time-resolved measurements showed an initial period with very low, decreasing transmission, the duration of which decreased with increasing intensity, followed by a rapid transition to full transmission, accompanied by brief sidescattering of the transmitted light with a significant red shift. Reflection was always negligible. Two-dimensional radiation–hydrodynamic simulations, using 3-D ray tracing with inverse bremsstrahlung energy deposition, did not capture the rapid transition to full transmission, showing instead a slow increase in transmission, without significant sidescatter or red shift. We propose that full transmission is achieved by self-focusing followed by ponderomotive blowout of the plasma.

Auto-magnetizing (AutoMag) liners [Slutz et al., Phys. Plasmas 24, 012704 (2017)] are designed to generate up to 100 T of axial magnetic field in the fuel for Magnetized Liner Inertial Fusion [Slutz et al., Phys. Plasmas 17, 056303 (2010)] without the need for external field coils. AutoMag liners (cylindrical tubes) are composed of discrete metallic helical conduction paths separated by electrically insulating material. Initially, helical current in the AutoMag liner produces internal axial magnetic field during a long (100 to 300 ns) current prepulse with an average current rise rate d I / d t = 5 k A / n s. After the cold fuel is magnetized, a rapidly rising current ( 200 k A / n s) generates a calculated electric field of 64 M V / m between the helices. Such field is sufficient to force dielectric breakdown of the insulating material after which liner current is reoriented from helical to predominantly axial which ceases the AutoMag axial magnetic field production mechanism and the z-pinch liner ...

A critical component of the magnetically driven implosion experiments at Sandia National Laboratories is the delivery of high-current, 10s of MA, from the Z pulsed power facility to a target. In order to assess the performance of the experiment, it is necessary to measure the current delivered to the target. Recent Magnetized Liner Inertial Fusion (MagLIF) experiments have included velocimetry diagnostics, such as PDV (Photonic Doppler Velocimetry) or Velocity Interferometer System for Any Reflector, in the final power feed section in order to infer the load current as a function of time. However, due to the nonlinear volumetrically distributed magnetic force within a velocimetry flyer, a complete time-dependent load current unfold is typically a time-intensive process and the uncertainties in the unfold can be difficult to assess. In this paper, we discuss how a PDV diagnostic can be simplified to obtain a peak current by sufficiently increasing the thickness of the flyer. This effectively keeps the magnetic force localized to the flyer surface, resulting in fast and highly accurate measurements of the peak load current. In addition, we show the results of experimental peak load current measurements from the PDV diagnostic in recent MagLIF experiments.

The Z-backlighter laser facility primarily consists of two high energy, high-power laser systems. Z-Beamlet laser (ZBL) (Rambo et al., Appl. Opt. 44, 2421 (2005)) is a multi-kJ-class, nanosecond laser operating at 1054 nm which is frequency doubled to 527 nm in order to provide x-ray backlighting of high energy density events on the Z-machine. Z-Petawatt (ZPW) (Schwarz et al., J. Phys.: Conf. Ser. 112, 032020 (2008)) is a petawatt-class system operating at 1054 nm delivering up to 500 J in 500 fs for backlighting and various short-pulse laser experiments (see also Figure 10 for a facility overview). With the development of the magnetized liner inertial fusion (MagLIF) concept on the Z-machine, the primary backlighting missions of ZBL and ZPW have been adjusted accordingly. As a result, we have focused our recent efforts on increasing the output energy of ZBL from 2 to 4 kJ at 527 nm by modifying the fiber front end to now include extra bandwidth (for stimulated Brillouin scattering suppression). The MagLIF concept requires a well-defined/behaved beam for interaction with the pressurized fuel. Hence we have made great efforts to implement an adaptive optics system on ZBL and have explored the use of phase plates. We are also exploring concepts to use ZPW as a backlighter for ZBL driven MagLIF experiments. Alternatively, ZPW could be used as an additional fusion fuel pre-heater or as a temporally flexible high energy pre-pulse. All of these concepts require the ability to operate the ZPW in a nanosecond long-pulse mode, in which the beam can co-propagate with ZBL. Some of the proposed modifications are complete and most of them are well on their way.

We report on the progress made to date for a Laboratory Directed Research and Development (LDRD) project aimed at diagnosing magnetic flux compression on the Z pulsed-power accelerator (0-20 MA in 100 ns). Each experiment consisted of an initially solid Be or Al liner (cylindrical tube), which was imploded using the Z accelerator's drive current (0-20 MA in 100 ns). The imploding liner compresses a 10-T axial seed field, B z ( 0 ) , supplied by an independently driven Helmholtz coil pair. Assuming perfect flux conservation, the axial field amplification should be well described by B z ( t ) = B z ( 0 ) x [ R ( 0 ) / R ( t )] 2 , where R is the liner's inner surface radius. With perfect flux conservation, B z ( t ) and dB z / dt values exceeding 10 4 T and 10 12 T/s, respectively, are expected. These large values, the diminishing liner volume, and the harsh environment on Z, make it particularly challenging to measure these fields. We report on our latest efforts to do so using three primary techniques: (1) micro B-dot probes to measure the fringe fields associated with fluxmore » compression, (2) streaked visible Zeeman absorption spectroscopy, and (3) fiber-based Faraday rotation. We also mention two new techniques that make use of the neutron diagnostics suite on Z. These techniques were not developed under this LDRD, but they could influence how we prioritize our efforts to diagnose magnetic flux compression on Z in the future. The first technique is based on the yield ratio of secondary DT to primary DD reactions. The second technique makes use of the secondary DT neutron time-of-flight energy spectra. Both of these techniques have been used successfully to infer the degree of magnetization at stagnation in fully integrated Magnetized Liner Inertial Fusion (MagLIF) experiments on Z [P. F. Schmit et al. , Phys. Rev. Lett. 113 , 155004 (2014); P. F. Knapp et al. , Phys. Plasmas, 22 , 056312 (2015)]. Finally, we present some recent developments for designing and fabricating novel micro B-dot probes to measure B z ( t ) inside of an imploding liner. In one approach, the micro B-dot loops were fabricated on a printed circuit board (PCB). The PCB was then soldered to off-the-shelf 0.020- inch-diameter semi-rigid coaxial cables, which were terminated with standard SMA connectors. These probes were recently tested using the COBRA pulsed power generator (0-1 MA in 100 ns) at Cornell University. In another approach, we are planning to use new multi-material 3D printing capabilities to fabricate novel micro B-dot packages. In the near future, we plan to 3D print these probes and then test them on the COBRA generator. With successful operation demonstrated at 1-MA, we will then make plans to use these probes on a 20-MA Z experiment.« less

A critical limitation of magnetically imploded systems such as magnetized liner inertial fusion (MagLIF) [Slutz et al., Phys. Plasmas 17, 056303 (2010)] is the magneto-Rayleigh-Taylor (MRT) instability which primarily disrupts the outer surface of the liner. MagLIF-relevant experiments have showed large amplitude multi-mode MRT instability growth growing from surface roughness [McBride et al., Phys. Rev. Lett. 109, 135004 (2012)], which is only reproduced by 3D simulations using our MHD code Gorgon when an artificially azimuthally correlated initialisation is added. We have shown that the missing azimuthal correlation could be provided by a combination of the electro-thermal instability (ETI) and an “electro-choric” instability (ECI); describing, respectively, the tendency of current to correlate azimuthally early in time due to temperature dependent Ohmic heating; and an amplification of the ETI driven by density dependent resistivity around vapourisation. We developed and implemented a material strength model in Gorgon to improve simulation of the solid phase of liner implosions which, when applied to simulations exhibiting the ETI and ECI, gave a significant increase in wavelength and amplitude. Full circumference simulations of the MRT instability provided a significant improvement on previous randomly initialised results and approached agreement with experiment.

Magnetized Liner Inertial Fusion1 (MagLIF) is a magneto-inertial fusion concept being evaluated on the Z machine at Sandia National Laboratories. In MagLIF, first an axial magnetic field is applied to a metal cylinder filled deuterium gas, next a laser heats the deuterium gas to 100s of eV, and then the target is magnetically-imploded using the Z machine current. The axial magnetic field reduces radial thermal conduction losses during laser heating and throughout the implosion, and it helps confine charged fusion products at stagnation. Laser heating increases the fuel temperature at the start of the implosion, which reduces the required radial convergence of the target to achieve multi-keV temperatures at stagnation.

The Rayleigh-Taylor (RT) instability and related hydrodynamic mechanisms of interfacial mixing are ubiquitous in nature, occurring on a large variety of scales, from atmospheric and oceanic to supernovae. They are of particular importance for many applications that involve high energy density plasmas, such as Z-pinch plasma sources of x-ray and neutron radiation or inertial confinement fusion (ICF). Most of these applications rely upon a dense plasma that is accelerated by the pressure of a lighter fluid, such as magnetic field in imploded Z-pinch or Magnetized Liner Inertial Fusion (MagLIF), a low-density ablated plasma imploding a laser fusion capsule, or decelerated by the pressure of hot-spot ICF plasma at stagnation. To improve performance of such systems and achieve the practical goals that range from increasing x-ray and neutron yields to the most ambitious goal of all, the ICF ignition, it is critically important to develop effective methods of mitigating the RT instability, making the loads and targets more resistant to the distortion. I will review the approaches to this problem that have been advanced over the last two decades. Most of them employ elaborate structuring of the density and/or material profiles in the loads and targets, which is achieved by use of nested wire arrays, multi-shell nozzle design for gas-puff Z-pinch injection, laser capsule manufacturing to control the interaction of laser targets with laser and x-ray radiation pulses. Application of an external axial magnetic field has been demonstrated to be an effective mechanism for mitigating the RT instability of electromagnetically driven implosions of cylindrical loads, from gas-puff Z pinches to MagLIF liners. We discuss the physics behind the most effective RT mitigation mechanisms, the status and prospects of the most promising methods of mitigation, and the unresolved physics issues, including the new opportunities that deserve to be studied.

As part of the work on the Magnetized Liner Inertial Fusion (MagLIF) concept1, Awe et al. found on the 20 MA Z-machine that applying an externally generated axial magnetic field to a liner produces a helical striation pattern in the liner2. We are investigating this phenomenon using 10 mm long cylindrical metal liners having 4 mm diameter and varying wall thickness on the 1 MA, 100–230 ns COBRA pulsed power generator at Cornell University. In addition, we will present experimental results on a configuration that includes a wire initially connecting the cathode and anode on the axis of a cylindrical liner that does not initially connect the cathode to the anode. Results of these experiments both with and without external magnetic fields will be shown. Extreme ultraviolet (XUV) imaging as well as optical streak and 12 frame camera imaging are used to observe and analyze liner surface emission. Axial and side-on interferometry are used to determine the distribution of plasma both near the liner surface and inside the liner, assessing, among other things, the impact of non-uniformities during the plasma ablation phase of the experiments.

Most fusion research has focused on magnetic confinement fusion with densities of ∼1014 ions/cm3 and confinement times of >10 s, or pulsed inertial confinement fusion (ICF) with densities ∼1025 ion/cm3 with confinement times

The size, temporal and spatial shape, and energy content of a laser pulse for the pre-heat phase of magneto-inertial fusion affect the ability to penetrate the window of the laser-entrance-hole and to heat the fuel behind it. High laser intensities and dense targets are subject to laser-plasma-instabilities (LPI), which can lead to an effective loss of pre-heat energy or to pronounced heating of areas that should stay unexposed. While this problem has been the subject of many studies over the last decades, the investigated parameters were typically geared towards traditional laser driven Inertial Confinement Fusion (ICF) with densities either at 10% and above or at 1% and below the laser's critical density, electron temperatures of 3–5 keV, and laser powers near (or in excess of) 1 × 1015 W/cm2. In contrast, Magnetized Liner Inertial Fusion (MagLIF) [Slutz et al., Phys. Plasmas 17, 056303 (2010) and Slutz and Vesey, Phys. Rev. Lett. 108, 025003 (2012)] currently operates at 5% of the laser's critical dens...

Presented is a semi-analytic model of magnetized liner inertial fusion (MagLIF). This model accounts for several key aspects of MagLIF, including: (1) preheat of the fuel (optionally via laser absorption); (2) pulsed-power-driven liner implosion; (3) liner compressibility with an analytic equation of state, artificial viscosity, internal magnetic pressure, and ohmic heating; (4) adiabatic compression and heating of the fuel; (5) radiative losses and fuel opacity; (6) magnetic flux compression with Nernst thermoelectric losses; (7) magnetized electron and ion thermal conduction losses; (8) end losses; (9) enhanced losses due to prescribed dopant concentrations and contaminant mix; (10) deuterium-deuterium and deuterium-tritium primary fusion reactions for arbitrary deuterium to tritium fuel ratios; and (11) magnetized alpha-particle fuel heating. We show that this simplified model, with its transparent and accessible physics, can be used to reproduce the general 1D behavior presented throughout the original MagLIF paper [S. A. Slutz et al., Phys. Plasmas 17, 056303 (2010)]. We also discuss some important physics insights gained as a result of developing this model, such as the dependence of radiative loss rates on the radial fraction of the fuel that is preheated., Comment: Published in Physics of Plasmas [http://dx.doi.org/10.1063/1.4918953]

Summarization: This article addresses key features for the implementation of low current pulsed power plasma devices for the study of matter dynamics from the solid to the plasma phase. The renewed interest in such low current plasma devices lies in the need to investigate methods for the mitigation of prompt seeding mechanisms for the generation of plasma instabilities. The low current when driven into thick wires (skin effect mode) allows for the simultaneous existence of all phases of matter from solid to plasma. Such studies are important for the concept of inertial confinement fusion where the mitigation of the instability seeding mechanisms arising from the very early moments within the target's heating is of crucial importance. Similarly, in the magnetized liner inertial fusion concept it is an open question as to how much surface non-uniformity correlates with the magneto-Rayleigh-Taylor instability, which develops during the implosion. This study presents experimental and simulation results, which demonstrate that the use of low current pulsed power devices in conjunction with appropriate diagnostics can be important for studying seeding mechanisms for the imminent generation of plasma instabilities in future research. Παρουσιάστηκε στο: Plasma Physics and Controlled Fusion

MagLIF is a fusion concept using a Z-pinch implosion to reach thermonuclear fusion. In current experiments, the implosion is driven by the Z-machine using 19 MA of electrical current with a rise time of 100 ns. MagLIF requires an initial axial magnetic field of 30 T to reduce heat losses to the liner wall during compression and to confine alpha particles during fusion burn. This field is generated well before the current ramp starts and needs to penetrate the transmission lines of the pulsed-power generator, as well as the liner itself. Consequently, the axial field rise time must exceed hundreds of microseconds. Any coil capable of being submitted to such a field for that length of time is inevitably bulky. The space required to fit the coil near the liner, increases the inductance of the load. In turn, the total current delivered to the load decreases since the voltage is limited by driver design. Yet, the large amount of current provided by the Z-machine can be used to produce the required 30 T field b...

The understanding of energy and magnetic flux losses in a magnetized plasma medium confined by a cold wall is of great interest in the success of magnetized liner inertial fusion (MagLIF). In a MagLIF scheme, the fuel is magnetized and subsonically compressed by a cylindrical liner. Magnetic flux conservation is degraded by the presence of gradient-driven transport processes such as thermoelectric effects (Nernst) and magnetic field diffusion. In previous publications [Velikovich et al., Phys. Plasmas 22, 042702 (2015)], the evolution of a hot magnetized plasma in contact with a cold solid wall (liner) was studied using the classical collisional Braginskii's plasma transport equations in one dimension. The Nernst term degraded the magnetic flux conservation, while both thermal energy and magnetic flux losses were reduced with the electron Hall parameter ωeτe with a power-law asymptotic scaling (ωeτe)−1/2. In the analysis made in the present paper, we consider a similar situation, but with the liner being ...

A laser-driven, magnetized liner inertial fusion (MagLIF) experiment is designed for the OMEGA Laser System by scaling down the Z point design to provide the first experimental data on MagLIF scaling. OMEGA delivers roughly 1000× less energy than Z, so target linear dimensions are reduced by factors of ∼10. Magneto-inertial fusion electrical discharge system could provide an axial magnetic field of 10 T. Two-dimensional hydrocode modeling indicates that a single OMEGA beam can preheat the fuel to a mean temperature of ∼200 eV, limited by mix caused by heat flow into the wall. One-dimensional magnetohydrodynamic (MHD) modeling is used to determine the pulse duration and fuel density that optimize neutron yield at a fuel convergence ratio of roughly 25 or less, matching the Z point design, for a range of shell thicknesses. A relatively thinner shell, giving a higher implosion velocity, is required to give adequate fuel heating on OMEGA compared to Z because of the increase in thermal losses in smaller targe...

Magneto-inertial fusion (MIF) combines the compression of fusion fuel, a hallmark of inertial confinement fusion (ICF), with strongly magnetized plasmas that suppress electron heat losses, a hallmark of magnetic fusion. It can reduce the traditional velocity, pressure, and convergence ratio requirements of ICF. The magnetized liner inertial fusion (MagLIF) concept being studied at the Z Pulsed-Power Facility is a key target concept in the U.S. ICF Program. Laser-driven MagLIF is being developed on OMEGA to test the scaling of MagLIF over a range of absorbed energy of the order of 1 kJ on OMEGA to 500 kJ on Z. It is also valuable as a platform for studying the key physics of MIF. An energy-scaled point design has been developed for OMEGA that is roughly 10 × smaller in linear dimensions than Z MagLIF targets. A 0.6-mm-outer-diameter plastic cylinder filled with 2.4 mg/cm3 of D2 is placed in a ∼10-T axial magnetic field, generated by a Magneto-inertial fusion electrical discharge system, the cylinder is com...

Magnetized Liner Inertial Fusion (MagLIF) experiments, where a metal liner is imploded to compress a magnetized seed plasma may generate peak magnetic fields ∼10(4) T (100 Megagauss) over small volumes (∼10(-10)m(3)) at high plasma densities (∼10(28)m(-3)) on 100 ns time scales. Such conditions are extremely challenging to diagnose. We discuss the possibility of, and issues involved in, using polarimetry techniques at x-ray wavelengths to measure magnetic fields under these extreme conditions.

This Letter presents results from the first fully integrated experiments testing the magnetized liner inertial fusion concept [S. A. Slutz et al., Phys. Plasmas 17, 056303 (2010)], in which a cylinder of deuterium gas with a preimposed 10 Taxial magnetic field is heated by Z beamlet, a 2.5 kJ, 1 TW laser, and magnetically imploded by a 19 MA, 100 ns rise time current on the Z facility. Despite a predicted peak implosion velocity of only 70 km = s, the fuel reaches a stagnation temperature of approximately 3 keV, with T(e) ≈ T(i), and produces up to 2 x 10(12) thermonuclear deuterium-deuterium neutrons. X-ray emission indicates a hot fuel region with full width at half maximum ranging from 60 to 120 μm over a 6 mm height and lasting approximately 2 ns. Greater than 10(10) secondary deuterium-tritium neutrons were observed, indicating significant fuel magnetization given that the estimated radial areal density of the plasma is only 2 mg = cm(2).

Magnetizing the fuel in inertial confinement fusion relaxes ignition requirements by reducing thermal conductivity and changing the physics of burn product confinement. Diagnosing the level of fuel magnetization during burn is critical to understanding target performance in magneto-inertial fusion (MIF) implosions. In pure deuterium fusion plasma, 1.01 MeV tritons are emitted during deuterium-deuterium fusion and can undergo secondary deuterium-tritium reactions before exiting the fuel. Increasing the fuel magnetization elongates the path lengths through the fuel of some of the tritons, enhancing their probability of reaction. Based on this feature, a method to diagnose fuel magnetization using the ratio of overall deuterium-tritium to deuterium-deuterium neutron yields is developed. Analysis of anisotropies in the secondary neutron energy spectra further constrain the measurement. Secondary reactions also are shown to provide an upper bound for the volumetric fuel-pusher mix in MIF. The analysis is applied to recent MIF experiments [M. R. Gomez et al., Phys. Rev. Lett. 113, 155003 (2014)] on the Z Pulsed Power Facility, indicating that significant magnetic confinement of charged burn products was achieved and suggesting a relatively low-mix environment. Both of these are essential features of future ignition-scale MIF designs.

The Z Facility at Sandia National Laboratories consists of the Z Machine, a pulsed power driver capable of delivering 27 MA with a 100 ns risetime to a magnetically-driven load, and the Z Beamlet Laser (ZBL), which can deliver a 1 TW, 2 ns laser pulse at 532 nm to the center of the Z Machine. Magnetized Liner Inertial Fusion1 (MagLIF) is an inertial confinement fusion concept that is currently being evaluated on Z. MagLIF relies on ZBL to heat fusion fuel prior to the implosion, an axial magnetic field to inhibit radial thermal conduction in the fuel, and the Z machine current pulse to implode the target. Simulations indicate that MagLIF experiments could produce 100 kJ yields with parameters that will eventually be possible on Z, and high yield targets for a future facility have been evaluated in simulations.2

Tests of the magnetized liner inertial fusion (MagLIF) concept will make use of the 27 MA Z-machine at Sandia National Laboratories, Albuquerque, to implode a cylindrical metal liner to compress and heat a preheated plasma contained within it [1]. While most pulsed power machines produce much lower currents than the Z-machine, there are questions that can still be answered on smaller scale setups. Recent work on the Cornell Beam Research Accelerator (COBRA) has made use of cylindrical metal liners made in-house to study the initiation of plasma on the liner surface and axial magnetic field compression. Although such liners are not sufficiently uniform for MagLIF-relevant studies of liner dynamics during implosion, they can make early-time studies of cylindrical liner implosions viable for smaller laboratories. This paper will present experimental results of imploding liners having imperfect uniformity to assess the impact that has on initiation and ablation. Extreme ultraviolet (XUV) imaging as well as optical streak imaging is used to assess when and where non-uniform-driven emission occurs. Axial interferometry is used to determine the distribution of plasma near the liner surface, including the impact of non-uniformities during the plasma initiation and ablation phases of the experiments.

The dynamics of Magnetized Liner Inertial Fusion (MagLIF)1, a new and promising approach to pulsed power fusion, are presently under detailed study at Sandia National Laboratories. Alongside this, a comprehensive analysis of the influence of the specific liner design geometry in the MagLIF system on liner initiation is underway in the academic community.

Magnetized liner inertial fusion (MagLIF) is a promising pathway to controlled thermonuclear fusion. The concept involves magnetically imploding a metal liner; a key limitation of such systems is the magneto-Rayleigh-Taylor (MRT) instability. MagLIF relevant liner implosions carried out by McBride et al [1] showed large amplitude MRT instability growth, requiring an azimuthally correlated seed to be added to simulations in order to achieve agreement.

The success of the Magnetized Liner Inertial Fusion (MagLIF) campaign requires successful mitigation of the Magneto-Rayleigh-Taylor instability (MRT). Initially, the exterior of the liner is MRT unstable; as the accelerated liner compresses a fill gas, it is eventually decelerated by the back pressure of the fill gas causing the inner surface to become MRT unstable. It is thought that feedthrough of MRT from the outer to inner surface can provide a seed for disruptive growth in the deceleration phase. A common method of studying MRT is by machining sinusoidal ripples on the exterior of metal targets (Al, Be in particular). This seeding provides a known wavelength for MRT whose growth can then be compared with linear theory. For the exterior of Al liners, linear MRT theory works quite well [1] and thus, feedthrough theory should apply equally well to the inner surface for an unshocked seeded liner. However, in most shots on the Z-machine a shock is driven through the liner. 2D HYDRA simulations show the shock is rippled with the seeded wavelength and imprints this ripple on the inner surface as it breaks-out. The amplitude of this ripple could be much larger than what would be expected from the feedthrough of MRT theory [2]. Thus, to study feedthrough directly either isentropic compression is required, or we must include the effect of the shock on feedthrough. We propose a simple model to determine the imprinted ripple amplitude from a shock and then calculate the evolution of the inner surface ripple using traditional MRT [2] and Richtmyer-Meshkov theory and then compare to 2D HYDRA results. This model allows for simultaneous study of outer/inner surface growth from an exterior seeded perturbation and includes the effect of feedthrough. We also examine the impact of axial magnetic fields and fill gases (cool and pre-heated) on feedthrough and shock imprinting by applying our model and compare with 2D simulations.

Recent experiments on Sandia's Z facility have confirmed simulation predictions of dramatically reduced instability growth in solid metallic rods when thick dielectric coatings are used to mitigate density perturbations arising from an electrothermal instability. These results provide further evidence that the inherent surface roughness as a result of target fabrication is not the dominant seed for the growth of magneto-Rayleigh-Taylor instabilities in liners with carefully machined smooth surfaces, but rather electrothermal instabilities that form early in the electrical current pulse as Joule heating melts and vaporizes the liner surface. These results suggest a new technique for substantially reducing the integral magneto-Rayleigh-Taylor instability growth in magnetically driven implosions, such as cylindrical dynamic material experiments and inertial confinement fusion concepts.

Ignition conditions in axially magnetized cylindrical targets are investigated by examining the thermal balance of assembled DT fuel configurations at stagnation. Special care is taken to adequately evaluate the energy fraction of 3.5 MeV alpha particles deposited in magnetized DT cylinders. A detailed analysis of the ignition boundaries in the ρR,T parametric plane is presented. It is shown that the fuel magnetization allows a significant reduction of the ρR ignition threshold only when the condition BR 6 × 105G cm is fulfilled (B is the magnetic field strength and R is the fuel radius).