Performance and Mix Measurements of Indirect Drive Cu-Doped Be Implosions

D. T. Casey, D. T. Woods, V. A. Smalyuk, O. A. Hurricane, V. Y. Glebov, C. Stoeckl, W. Theobald, R. Wallace, A. Nikroo, M. Schoff, C. Shuldberg, K. J. Wu, J. A. Frenje, O. L. Landen, B. A. Remington, and G. Glendinning
Phys. Rev. Lett. 114, 205002 – Published 19 May 2015

Abstract

The ablator couples energy between the driver and fusion fuel in inertial confinement fusion (ICF). Because of its low opacity, high solid density, and material properties, beryllium has long been considered an ideal ablator for ICF ignition experiments at the National Ignition Facility. We report here the first indirect drive Be implosions driven with shaped laser pulses and diagnosed with fusion yield at the OMEGA laser. The results show good performance with an average DD neutron yield of 2×109 at a convergence ratio of R0/R10 and little impact due to the growth of hydrodynamic instabilities and mix. In addition, the effect of adding an inner liner of W between the Be and DD is demonstrated.

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  • Received 22 October 2014

DOI:https://doi.org/10.1103/PhysRevLett.114.205002

© 2015 American Physical Society

Authors & Affiliations

D. T. Casey1, D. T. Woods1, V. A. Smalyuk1, O. A. Hurricane1, V. Y. Glebov2, C. Stoeckl2, W. Theobald2, R. Wallace1, A. Nikroo3, M. Schoff3, C. Shuldberg3, K. J. Wu1, J. A. Frenje4, O. L. Landen1, B. A. Remington1, and G. Glendinning1

  • 1Lawrence Livermore National Laboratory, Livermore, California 94550, USA
  • 2Laboratory for Laser Energetics, University of Rochester, Rochester, New York 14623, USA
  • 3General Atomics, San Diego, California 92121, USA
  • 4Massachusetts Institute of Technology, Cambridge, Massachusetts 02139, USA

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Vol. 114, Iss. 20 — 22 May 2015

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