Physics of Plasmas · 2014 · 141 citations · 46 references
EngineeringNuclear EngineeringPhysicsFusion EngineeringNuclear MaterialsNuclear PhysicsAblative MaterialsFusion Reactor MaterialsInertial Confinement FusionNuclear FusionPlasma ConfinementReactor Core DesignAblation PhysicsDensityDeuterium-tritium FusionDirect DriveIgnition PhysicsInertial Confinement
High Density Carbon (HDC) is a leading candidate as an ablator material for Inertial Confinement Fusion (ICF) capsules in x-ray (indirect) drive implosions. HDC has a higher density (3.5 g/cc) than plastic (CH, 1 g/cc), which results in a thinner ablator with a larger inner radius for a given capsule scale. This leads to higher x-ray absorption and shorter laser pulses compared to equivalent CH designs. This paper will describe a series of experiments carried out to examine the feasibility of using HDC as an ablator using both gas filled hohlraums and lower density, near vacuum hohlraums. These experiments have shown that deuterium (DD) and deuterium-tritium gas filled HDC capsules driven by a hohlraum filled with 1.2 mg/cc He gas, produce neutron yields a factor of 2× higher than equivalent CH implosions, representing better than 50% Yield-over-Clean (YoC). In a near vacuum hohlraum (He = 0.03 mg/cc) with 98% laser-to-hohlraum coupling, such a DD gas-filled capsule performed near 1D expectations. A cryogenic layered implosion version was consistent with a fuel velocity = 410 ± 20 km/s with no observed ablator mixing into the hot spot.
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Initial performance results of the OMEGA laser system
T. R. Boehly, David L. Brown, R. S. Craxton et al. · Optics Communications · 1997 · 1.1K citations · Full text
Natural Sciences, Nuclear Engineering, Fusion Engineering +16
Three-dimensional HYDRA simulations of National Ignition Facility targets
M. M. Marinak, G. D. Kerbel, N. A. Gentile et al. · Physics of Plasmas · 2001 · 697 citations