Term

Keith LeChien

Overview

Pacific Fusionの共同創設者であり、最高技術責任者(CTO)。パルスパワーと核融合技術の専門家であり、サンディア国立研究所などでの経験を持つ。

Research Papers

5 件
  • Development and tests of fast 1-MA linear transformer driver stages

    A. Kim, M. Mazarakis, V. Sinebryukhov, B. Kovalchuk, V. A. Visir, S. Volkov, F. Bayol, A. Bastrikov, V. Durakov, S. Frolov, V. Alexeenko, D. Mcdaniel, W. Fowler, K. LeChien, C. Olson, W. Stygar, K. Struve, J. Porter, R. Gilgenbach

    2009 143 件引用 Semantic Scholar

    In this article we present the design and test results of the most powerful, fast linear transformer driver (LTD) stage developed to date. This 1-MA LTD stage consists of 40 parallel RLC (resistor R, inductor L, and capacitor C) circuits called ``bricks'' that are triggered simultaneously; it is able to deliver $\ensuremath{\sim}1\text{ }\text{ }\mathrm{MA}$ current pulse with a rise time of $\ensuremath{\sim}100\text{ }\text{ }\mathrm{ns}$ into the $\ensuremath{\sim}0.1\mathrm{\text{\ensuremath{-}}}\mathrm{Ohm}$ matched load. The electrical behavior of the stage can be predicted by using a simple RLC circuit, thus simplifying the designing of various LTD-based accelerators. Five 1-MA LTD stages assembled in series into a module have been successfully tested with both resistive and vacuum electron-beam diode loads.

  • Conceptual designs of two petawatt-class pulsed-power accelerators for high-energy-density-physics experiments

    W. Stygar, T. Awe, J. E. Bailey, N. Bennett, E. Breden, E. M. Campbell, R. E. Clark, R. Cooper, M. Cuneo, J. Ennis, D. Fehl, T. Genoni, M. Gomez, G. Greiser, F. Gruner, M. Herrmann, B. Hutsel, C. Jennings, D. Jobe, B. M. Jones, M. C. Jones, P. A. Jones, P. Knapp, J. Lash, K. LeChien, J. Leckbee, R. Leeper, S. Lewis, F. Long, D. Lucero, E. Madrid, M. R. Martin, M. Matzen, M. Mazarakis, R. D. McBride, G. McKee, C. Miller, J. K. Moore, C. Mostrom, T. Mulville, K. Peterson, J. L. Porter, D. Reisman, G. Rochau, G. Rochau, D. Rose, D. Rovang, M. E. Savage, M. Sceiford, P. Schmit, R. Schneider, J. Schwarz, A. Sefkow, D. Sinars, S. Slutz, R. Spielman, B. Stoltzfus, C. Thoma, R. Vesey, P. Wakeland, D. Welch, M. Wisher, J. Woodworth

    2015 123 件引用 Semantic Scholar

    Here, we have developed conceptual designs of two petawatt-class pulsed-power accelerators: Z 300 and Z 800. The designs are based on an accelerator architecture that is founded on two concepts: single-stage electrical-pulse compression and impedance matching [Phys. Rev. ST Accel. Beams 10, 030401 (2007)]. The prime power source of each machine consists of 90 linear-transformer-driver (LTD) modules. Each module comprises LTD cavities connected electrically in series, each of which is powered by 5-GW LTD bricks connected electrically in parallel. (A brick comprises a single switch and two capacitors in series.) Six water-insulated radial-transmission-line impedance transformers transport the power generated by the modules to a six-level vacuum-insulator stack. The stack serves as the accelerator’s water-vacuum interface. The stack is connected to six conical outer magnetically insulated vacuum transmission lines (MITLs), which are joined in parallel at a 10-cm radius by a triple-post-hole vacuum convolute. The convolute sums the electrical currents at the outputs of the six outer MITLs, and delivers the combined current to a single short inner MITL. The inner MITL transmits the combined current to the accelerator’s physics-package load. Z 300 is 35 m in diameter and stores 48 MJ of electrical energy in its LTD capacitors. The acceleratormore » generates 320 TW of electrical power at the output of the LTD system, and delivers 48 MA in 154 ns to a magnetized-liner inertial-fusion (MagLIF) target [Phys. Plasmas 17, 056303 (2010)]. The peak electrical power at the MagLIF target is 870 TW, which is the highest power throughout the accelerator. Power amplification is accomplished by the centrally located vacuum section, which serves as an intermediate inductive-energy-storage device. The principal goal of Z 300 is to achieve thermonuclear ignition; i.e., a fusion yield that exceeds the energy transmitted by the accelerator to the liner. 2D magnetohydrodynamic (MHD) simulations suggest Z 300 will deliver 4.3 MJ to the liner, and achieve a yield on the order of 18 MJ. Z 800 is 52 m in diameter and stores 130 MJ. This accelerator generates 890 TW at the output of its LTD system, and delivers 65 MA in 113 ns to a MagLIF target. The peak electrical power at the MagLIF liner is 2500 TW. The principal goal of Z 800 is to achieve high-yield thermonuclear fusion; i.e., a yield that exceeds the energy initially stored by the accelerator’s capacitors. 2D MHD simulations suggest Z 800 will deliver 8.0 MJ to the liner, and achieve a yield on the order of 440 MJ. Z 300 and Z 800, or variations of these accelerators, will allow the international high-energy-density-physics community to conduct advanced inertial-confinement-fusion, radiation-physics, material-physics, and laboratory-astrophysics experiments over heretofore-inaccessible parameter regimes.« less

  • Affordable, manageable, practical, and scalable (AMPS) high-yield and high-gain inertial fusion

    A. Alexander, L. Benedetti, I. Bhattacharyya, J. Bowen, June Cabatu, Virgil Cacdac, Chhavi Chhavi, Chiatai Chen, Karen Chen, D. Clark, J. Clark, T. Cope, Will Dannemann, Scott Davidson, David DeHaan, J. Dugan, Mindy Eihusen, C. Ellison, C. Esquivel, David Ethridge, B. Ferguson, Bryan Ferguson, J. Fry, F. García-Rubio, T. Goyal, Gary Grim, Justin Grodman, B. Haid, F. Howland, Van Huynh, V. John, Patrick Knapp, Isaac Kravitz, Eric S. Lander, S. Langendorf, Keith R. LeChien, A. Link, N. Meezan, Douglas S. Miller, Nantas Nardelli, Queenelle Ogirri, J. Peng, A. Pinto, R. Powser, Fritz Roy Puno, Kenny T. Quang, Brett Rahn, W. Regan, Kelsey Reichenbach, Adam Reyes, C. Richardson, David Rose, J. Samaniego, P. Schmit, V. Silva, N. Simon, S. Sitaraman, Hardeep Sullan, James Trebesch, Minh-Dung Truong, Carrie Von Muench, C. Waltz, Doug Williams, E. Wood, Sid Wu, A. Zylstra

    2025 9 件引用 Semantic Scholar

    High-yield inertial fusion offers a transformative path to affordable, clean, firm power and advanced defense capabilities. Recent milestones at large facilities, particularly the National Ignition Facility (NIF), have demonstrated the feasibility of ignition but highlight the need for approaches that can deliver large amounts of energy to fusion targets at much higher efficiency and lower cost. We propose that pulser-driven inertial fusion energy (IFE), which uses high-current pulsed-power technology to compress targets to thermonuclear conditions, can achieve this goal. In this paper, we detail the physics basis for pulser IFE, focusing on magnetized liner inertial fusion, where cylindrical metal liners compress DT fuel under strong magnetic fields and preheat. We discuss how the low implosion velocities, direct-drive efficiency, and scalable pulser architecture can achieve ignition-level conditions at low capital cost. Our multi-dimensional simulations, benchmarked against experiments at the Z facility, show that scaling from 20 to 50–60 MA of current enables net facility gain. We then introduce our Demonstration System (DS), a pulsed-power driver designed to deliver more than 60 MA and store approximately 80 MJ of energy. The DS is designed to achieve a 1000× increase in effective performance compared to the NIF, delivering approximately 100× greater facility-level energy gain—and importantly, achieving net facility gain, or Qf>1—at just 1/10 the capital cost. We also examine the engineering requirements for repetitive operation, target fabrication, and chamber maintenance, highlighting a practical roadmap to commercial power plants.

  • Validation of FLASH for magnetically driven inertial confinement fusion target design

    C. Ellison, Jonathan Carroll-Nellenback, Chiatai Chen, Scott Davidson, Bryan Ferguson, F. García-Rubio, E. C. Hansen, Y. D. Jong, J. King, Patrick Knapp, Keith R. LeChien, A. Link, N. Meezan, Douglas S. Miller, Philip Mocz, K. Moczulski, Nantas Nardelli, Adam Reyes, P. Schmit, Hardeep Sullan, P. Tzeferacos, D. V. Vugt, A. Zylstra

    2025 7 件引用 Semantic Scholar

    FLASH is a widely available radiation magnetohydrodynamics code used for astrophysics, laboratory plasma science, high energy density physics, and inertial confinement fusion (ICF). Increasing interest in magnetically driven inertial confinement fusion, including Pacific fusion's development of a 60 MA demonstration system designed to achieve facility gain, motivates the improvement and validation of FLASH for modeling magnetically driven ICF concepts, such as MagLIF, at ignition scale. Here, we present a collection of six validation benchmarks from experiments at the Z Pulsed Power Facility and theoretical and simulation studies of scaling MagLIF to high currents. The benchmarks range in complexity from focused experiments of linear hydrodynamic instabilities to fully integrated MagLIF fusion experiments. With the latest addition of physics capabilities, FLASH now obtains good agreement with the experimental data, theoretical results, and leading ICF target design simulation code results across all six benchmarks. These results establish confidence in FLASH as a useful tool for designing magnetically driven ICF targets on facilities like Z and Pacific fusion's upcoming 60 MA Demonstration System.

  • Impact of power flow on Z-pinch loads

    K. Tummel, D. Welch, D. Rose, A. Link, K. LeChien

    2022 7 件引用 Semantic Scholar

    Magnetically insulated transmission lines (MITLs) are used to deliver tens of MA to a Z-pinch load. The MITLs suffer current losses due to contaminant plasma located in the anode–cathode gap which is swept toward the load along the power flow. The swept up contaminant plasma can deposit mass and energy onto the load resulting in deformations or the seeding of macroscopic instabilities. This paper discusses 2D fully kinetic simulations of the contaminant plasma evolution which predict the current losses and the flux of mass and energy onto the load. The effects of a dynamic, i.e., imploding, load are shown to increase both the current loss and the mass and energy flux. The MITL used is a conical, radially converging design which is a feature common to MA-scale Z-pinch accelerators.

Mentioned Articles

1 件