Abstract

In inertial confinement fusion (ICF), the DT fuel should be compressed uniformly, and the ion temperature of the compressed DT should reach ~5–10 [KeV]. In order to compress the DT fuel stably to the high density, the implosion non-uniformity should be less than a few percent. In this paper, we present a fuel pellet implosion simulation system O-SUKI code in heavy ion inertial confinement fusion and its application results to parameter studies especially in the driver input pulse. It was found that the rise time period of the main pulse has a significant impact on the fuel implosion performance. We also found that an irradiation timing error of each driver beam induces an enhancement of the implosion non-uniformity, and consequently the driver beam irradiation timing error degrades the fusion energy gain.

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