Publications

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In the high-pressure regime above 300-500 psig, voltage-breakdown models such as the Paschen's law fail [1]. Below 300 psig the E/p values suggest that the breakdown mechanism, specifically at high E/p values is dominated by the ionization mechanism. As the air pressure is increased, the breakdown mechanism shifts from an ionization dominated regime to an attachment dominated regime at E/p values below 30. Thus, current Paschen equations will over predict the breakdown voltage and the electric field at which high-pressure spark gaps can be operated. Notably, as the attachment mechanism starts to dominate the breakdown physics the breakdown field in a high-pressure spark gap asymptotes at 1-1.2 MV/cm. Using recent data collected at Sandia National Laboratories, we have implemented corrections to breakdown prediction modeling using COMSOL to predict the breakdown voltage that can be achieved in the high-pressure regime, from 500-1500 psig. This research highlights how these corrections to the breakdown prediction models are implemented and the results of the simulations are compared to our data as well as other small gap data. We also compare the model to published literature values and to large gap breakdown in the 0.6-cm to 1.0-cm regime.

High-pressure, ultra-zero air is being evaluated as a potential replacement to SF6 in a strategic focus to move away from environmentally damaging insulating gasses. There are a lot of unknowns about the dominant breakdown mechanisms of ultra-zero air in the high-pressure regime. The classical equations for Paschen curves appear to not be valid above 500 psig. In order to better understand the phenomena of gas breakdown in the high-pressure regime, Sandia National Laboratories is evaluating the basic gas physics breakdown using nonuniform-field electrode designs. Recent data has been collected at SNL to study the breakdown of this high-pressure regime in the range of 300 - 1500 psi with gaps on the order of 0.6 - 1 cm with different electrode designs. The self-breakdown voltages range from 200-900 kV with a pulse-charge rise times of 200-300 ns and discharge currents from 25-60 kA. This research investigates the phenomenon of high-pressure breakdown, highlights the data collected, and presents a few of the mechanisms that dominate in the high-pressure regime for electronegative gasses.

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Next generation pulsed power (NGPP) machines and accelerators require a better understanding of the materials used within the vacuum vessels to achieve lower base pressures (P << 10-5 Torr) and reduce the overall contaminant inventory while incorporating various dielectric materials which tend to be unfavorable for ultra-high vacuum (UHV) applications. By improving the baseline vacuum, it may be possible to delay the onset of impedance collapse, reduce current loss on multi-mega Amp devices, or improve the lifetime of thermionic cathodes, etc [3]. In this study, we examine the vacuum outgassing rate of Rexolite® (cross-linked polystyrene) and Kel-F® (polychlorotrifluoroethylene) as candidate materials for vacuum insulators [1]. These values are then incorporated into boundary conditions for molecular flow simulations using COMSOL Multiphysics® and used to predict the performance of a prototypical pulsed power system designed for 10-8 Torr operations.

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Herein we present details of the design, simulation, and performance of a 100-GW linear transformer driver (LTD) cavity at Sandia National Laboratories. The cavity consists of 20 "bricks." Each brick is comprised of two 80 nF, 100 kV capacitors connected electrically in series with a custom, 200 kV, three-electrode, field-distortion gas switch. The brick capacitors are bipolar charged to ±100 kV for a total switch voltage of 200 kV. Typical brick circuit parameters are 40 nF capacitance (two 80 nF capacitors in series) and 160 nH inductance. The switch electrodes are fabricated from a WCu alloy and are operated with breathable air. Over the course of 6,556 shots the cavity generated a peak electrical current and power of 1.03 MA (±1.8%) and 106 GW (±3.1%). Experimental results are consistent (to within uncertainties) with circuit simulations for normal operation, and expected failure modes including prefire and late-fire events. New features of this development that are reported here in detail include: (1) 100 ns, 1 MA, 100-GW output from a 2.2 m diameter LTD into a 0.1 Ω load, (2) high-impedance solid charging resistors that are optimized for this application, and (3) evaluation of maintenance-free trigger circuits using capacitive coupling and inductive isolation.

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We have developed two advanced designs of a field-distortion air-insulated spark-gap switch that reduce the size of a linear-transformer-driver (LTD) brick. Both designs operate at 200 kV and a peak current of ~50 kA. At these parameters, both achieve a jitter of less than 2 ns and a prefire rate of ~0.1% over 5000 shots. We have reduced the number of switch parts and assembly steps, which has resulted in a more uniform, design-driven assembly process. We will characterize the performance of tungsten-copper and graphite electrodes, and two different electrode geometries. The new switch designs will substantially improve the electrical and operational performance of next-generation pulsed-power accelerators.

National Security Technologies (NSTec) is developing dense plasma focus (DPF) systems for applications requiring intense pulsed neutron sources. Sandia National Laboratories participated in a limited number of experiments with one of those systems. In collaboration with NSTec, Los Alamos National Laboratory, and Lawrence Livermore National Laboratory, we installed additional electrical and X-ray image measurements in parallel with normal operation of the system. Dense plasma focus machines have been studied for decades, but much of the experimental interest has been on neutron and X-ray yield. The primary goal for the present work was to develop and field high-fidelity and traceably-calibrated current and voltage measurements for comparison to digital simulations. The secondary goals were to utilize the current and voltage measurements to add general understanding of vacuum insulator behavior and current sheath dynamics. We also conducted initial scoping studies of soft X-ray diagnostics. We will show the electrical diagnostics and the techniques used to acquire high-fidelity signals in the difficult environment of the 2 MA, 6 μ plasma focus drive pulse. We will show how we measure accreted plasma mass non-invasively, and the sensitivity to background fill density. We will present initial qualitative results from filtered X-ray pinhole images and spectroscopic data from the pinch region.

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Several magnetized liner inertial fusion (MagLIF) experiments have been conducted on the Z accelerator at Sandia National Laboratories since late 2013. Measurements of the primary DD (2.45 MeV) neutrons for these experiments suggest that the neutron production is thermonuclear. Primary DD yields up to 3e12 with ion temperatures ∼2-3 keV have been achieved. Measurements of the secondary DT (14 MeV) neutrons indicate that the fuel is significantly magnetized. Measurements of down-scattered neutrons from the beryllium liner suggest ρRliner∼1g/cm2. Neutron bang times, estimated from neutron time-of-flight (nTOF) measurements, coincide with peak x-ray production. Plans to improve and expand the Z neutron diagnostic suite include neutron burn-history diagnostics, increased sensitivity and higher precision nTOF detectors, and neutron recoil-based yield and spectral measurements.

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Magnetized Liner Inertial Fusion experiments performed at Sandia's Z facility have demonstrated significant thermonuclear fusion neutron yields (∼10¹² DD neutrons) from multi-keV deuterium plasmas inertially confined by slow (∼10 cm/μs), stable, cylindrical implosions. Effective magnetic confinement of charged fusion reactants and products is signaled by high secondary DT neutron yields above 10¹⁰. Analysis of extensive power, imaging, and spectroscopic x-ray measurements provides a detailed picture of ∼3 keV temperatures, 0.3 g/cm³ densities, gradients, and mix in the fuel and liner over the 1-2 ns stagnation duration.

The standard approaches to inertial confinement fusion (ICF) rely on implosion velocities greater than 300 km/s and spherical convergence to achieve the high fuel temperatures (T > 4 keV) and areal densities (ρr > 0.3 g/cm2) required for ignition1. Such high velocities are achieved by heating the outside surface of a spherical capsuleeither directly with a large number of laser beams (Direct Drive) or with x-rays generated within a hohlraum (Indirect Drive). A much more energetically efficient approach is to use the magnetic pressure generated by a pulsed power machine to directly drive an implosion. In this approach 5-10% of the stored energy can be converted to the implosion of a metal tube generally referred to as a “liner”. However, the implosion velocity is not very high 70-100 km/s and the convergence is cylindrical (rather than spherical) making it more difficult to achieve the high temperatures and areal densities needed for ignition.

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 axial magnetic field of 10 T is heated by Z beamlet, a 2.5 kJ, 1 TW laser, and magnetically imploded by a 19 MA current with 100 ns rise time 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 2e12 thermonuclear DD neutrons. In this study, 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. The number of secondary deuterium-tritium neutrons observed was greater than 10¹⁰, indicating significant fuel magnetization given that the estimated radial areal density of the plasma is only 2 mg/cm².

Tests are ongoing to conduct ~20 MA z-pinch implosions on the Z accelerator at Sandia National Laboratory using Ar, Kr, and D2 gas puffs as the imploding loads. The relatively high cost of operations on a machine of this scale imposes stringent requirements on the functionality, reliability, and safety of gas puff hardware. Here we describe the development of a prototype gas puff system including the multiple-shell nozzles, electromagnetic drivers for each nozzle's valve, a UV pre-ionizer, and an inductive isolator to isolate the ~2.4 MV machine voltage pulse present at the gas load from the necessary electrical and fluid connections made to the puff system from outside the Z vacuum chamber. This paper shows how the assembly couples to the overall Z system and presents data taken to validate the functionality of the overall system.

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