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Title: Laser-driven magnetized liner inertial fusion

Abstract

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

Authors:
 [1];  [1];  [1];  [1];  [1];  [2];  [1];  [3];  [3];  [3]
  1. Univ. of Rochester, NY (United States). Lab. for Laser Energetics
  2. (Taiwan). Inst. of Space and Plasma Sciences
  3. Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
Publication Date:
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 Org.:
Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); National Cheng Kung Univ., Tainan City (Taiwan)
OSTI Identifier:
1361694
Grant/Contract Number:  
NA0001944; AR0000568
Resource Type:
Journal Article: Accepted Manuscript
Journal Name:
Physics of Plasmas
Additional Journal Information:
Journal Volume: 24; Journal Issue: 6; Journal ID: ISSN 1070-664X
Publisher:
American Institute of Physics (AIP)
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; Magnetic fields; Neutrons; Experiment design; Thermal conductivity; Plasma temperature

Citation Formats

Davies, J. R., Barnak, D. H., Betti, R., Campbell, E. M., Chang, P. -Y., National Cheng Kung Univ., Tainan City, Sefkow, A. B., Peterson, K. J., Sinars, D. B., and Weis, M. R. Laser-driven magnetized liner inertial fusion. United States: N. p., 2017. Web. doi:10.1063/1.4984779.
Davies, J. R., Barnak, D. H., Betti, R., Campbell, E. M., Chang, P. -Y., National Cheng Kung Univ., Tainan City, Sefkow, A. B., Peterson, K. J., Sinars, D. B., & Weis, M. R. Laser-driven magnetized liner inertial fusion. United States. doi:10.1063/1.4984779.
Davies, J. R., Barnak, D. H., Betti, R., Campbell, E. M., Chang, P. -Y., National Cheng Kung Univ., Tainan City, Sefkow, A. B., Peterson, K. J., Sinars, D. B., and Weis, M. R. Mon . "Laser-driven magnetized liner inertial fusion". United States. doi:10.1063/1.4984779. https://www.osti.gov/servlets/purl/1361694.
@article{osti_1361694,
title = {Laser-driven magnetized liner inertial fusion},
author = {Davies, J. R. and Barnak, D. H. and Betti, R. and Campbell, E. M. and Chang, P. -Y. and National Cheng Kung Univ., Tainan City and Sefkow, A. B. and Peterson, K. J. and Sinars, D. B. and Weis, M. R.},
abstractNote = {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 the MJ laser energy available on the National Ignition Facility gives a 500-fold increase in neutron yield in 1-D modeling.},
doi = {10.1063/1.4984779},
journal = {Physics of Plasmas},
number = 6,
volume = 24,
place = {United States},
year = {Mon Jun 05 00:00:00 EDT 2017},
month = {Mon Jun 05 00:00:00 EDT 2017}
}

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