Measurement of ICF fuel ion temperature on Nova

Computer Science – Performance

Scientific paper

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Convergence, Implosions, Inertial Confinement Fusion, Ion Temperature, Plasma Diagnostics, Confinement, Deuterium, Fusion Reactors, Laser Fusion, Nova Laser System

Scientific paper

A new diagnostic for measuring the average fuel ion temperature in inertial confinement fusion (ICF) targets at the time of peak burn has been constructed by Los Alamos and installed on the Nova Laser System at Lawrence Livermore National Laboratory. This ion-temperature diagnostic measures the time-of-flight of fusion neutrons and determines the thermonuclear-reaction-weighted ion temperature through the time-of-arrival distribution. Preliminary experiments have been designed and performed to test the diagnostic. These tests measured the ion temperature of targets designed to have varying temperatures and yields. Additionally, an experiment has been designed to examine the cause of the increase in yield degradation (compared to clean 1-D calculations) as the capsule convergence is increased. Understanding the cause of yield degradation in high convergence implosions is necessary to increase the confidence of the target performance for the next generation National Ignition Facility planned by the US ICF Program.

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