Simulations of Polar-Drive NIF Targets Optimized for High Neutron Yields

Thin-shell, DT-filled, room-temperature targets driven directly on the NIF using polar drive\footnote{ A.M. Cok, R.S. Craxton, and P.W. McKenty, ``Polar-Drive Designs for Optimizing Neutron Yields on the National Ignition Facility,'' submitted to Phys. Plasmas.} promise high fusion yields for neutron diagnostic development. These targets have been modeled with three codes: \textit{LILAC}, to optimize the 1-D design; \textit{SAGE}, to optimize the pointing uniformity; and \textit{DRACO}, to predict the yield from 2-D implosion simulations. The predicted yields (in the range of 10$^{15}$ to 10$^{16}$ neutrons for laser energies from 350 kJ to 1 MJ) are consistent with earlier data on OMEGA (10$^{14}$ neutrons at 30 kJ). This work was supported by the U.S. Department of Energy Office of Inertial Confinement Fusion under Cooperative Agreement No. DE-FC52-08NA28302.