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Title: Laser-driven magnetized liner inertial fusion

A laser-driven, magnetized liner inertial fusion (MagLIF) experiment is designed in this paper 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 targets. Two-dimensional MHD modeling of the point design gives roughly a 50% reduction in compressed density, temperature, and magnetic field from 1-D because of end losses. Finally, scaling up the OMEGA point design to themore » MJ laser energy available on the National Ignition Facility gives a 500-fold increase in neutron yield in 1-D modeling.« less
  1. Univ. of Rochester, NY (United Stat
Publication Date:
Grant/Contract Number:
NA0001944; AR0000568
Accepted Manuscript
Journal Name:
Physics of Plasmas
Additional Journal Information:
Journal Volume: 24; Journal Issue: 6; Journal ID: ISSN 1070-664X
American Institute of Physics (AIP)
Research Org:
Univ. of Rochester, NY (United States)
Sponsoring Org:
USDOE National Nuclear Security Administration (NNSA); USDOE Advanced Research Projects Agency - Energy (ARPA-E); Univ. of Rochester (United States); New York State Research and Development Authority (United States)
Contributing Orgs:
Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); National Cheng Kung Univ., Tainan City (Taiwan)
Country of Publication:
United States
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; Magnetic fields; Neutrons; Experiment design; Thermal conductivity; Plasma temperature
OSTI Identifier: