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

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 ∼2×10^{9} at a convergence ratio of R_{0}/R∼10 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.

[1]  O. Landen,et al.  The physics basis for ignition using indirect-drive targets on the National Ignition Facility , 2004 .

[2]  Jay D. Salmonson,et al.  Optimized beryllium target design for indirectly driven inertial confinement fusion experiments on the National Ignition Facility , 2014 .

[3]  Thomas J. Dolan,et al.  Plasma Physics and Fusion Energy , 2008 .

[4]  Olga Smirnova,et al.  Nature in London , 2016 .

[5]  Zach DeVito,et al.  Opt , 2017 .

[6]  Dan J. Thoma,et al.  The development and advantages of beryllium capsules for the National Ignition Facility , 1998 .

[7]  Robert L. Kauffman,et al.  Measurement of 0.1-3-keV x rays from laser plasmas , 1986 .

[8]  Karen S. Anderson,et al.  Thermonuclear ignition in inertial confinement fusion and comparison with magnetic confinement , 2010 .

[9]  Edward I. Moses,et al.  Ignition on the National Ignition Facility , 2007 .

[10]  Steven W. Haan,et al.  Nova indirect drive RayleighTaylor experiments with beryllium , 2002 .

[11]  Steven H. Batha,et al.  Hydrodynamic instabilities in beryllium targets for the National Ignition Facility , 2014 .

[12]  G. R. Bennett,et al.  Evaluation of bent-crystal x-ray backlighting and microscopy techniques for the Sandia Z machine. , 2003, Applied optics.

[13]  K. Fournier,et al.  Source geometric considerations for OMEGA Dante measurements. , 2012, The Review of scientific instruments.

[14]  Jonathan D. Zuegel,et al.  High-energy petawatt capability for the omega laser , 2005 .

[15]  D. A. Callahan,et al.  Fuel gain exceeding unity in an inertially confined fusion implosion , 2014, Nature.

[16]  M J Moran,et al.  The National Ignition Facility neutron time-of-flight system and its initial performance (invited). , 2010, The Review of scientific instruments.

[17]  Samuel A. Letzring,et al.  Initial performance results of the OMEGA laser system , 1997 .

[18]  J. Koch,et al.  Numerical simulation of thin-shell direct drive DHe3-filled capsules fielded at OMEGA , 2012 .

[19]  Jason C. Cooley,et al.  Progress toward fabrication of graded doped beryllium and CH capsules for the National Ignition Facilitya) , 2006 .

[20]  O. Landen,et al.  X-ray ablation rates in inertial confinement fusion capsule materials , 2011 .

[21]  B. E. Kruschwitz,et al.  High-Energy Petawatt Project at the University of Rochester's Laboratory for Laser Energetics , 2006 .

[22]  Andrew G. Glen,et al.  APPL , 2001 .

[23]  Arthur Nobile,et al.  Status of the development of ignition capsules in the U.S. effort to achieve thermonuclear ignition on the national ignition facility , 2006 .

[24]  Barry E. Schwartz,et al.  Spectrometry of charged particles from inertial-confinement-fusion plasmas , 2003 .

[25]  J. J. MacFarlane.  VISRAD—A 3-D view factor code and design tool for high-energy density physics experiments , 2003 .