作者: R. A. Lerche , B. A. Remington
DOI: 10.1063/1.1141704
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摘要: Fuel ion temperatures for laser‐driven, inertial confinement fusion targets are often determined by neutron time‐of‐flight (TOF) techniques. The error in the temperature measurement is a minimum at target‐to‐detector distance that depends on both target and detector characteristics. dominated response shorter distances number of detected neutrons larger distances. We develop equations relate to temperature, detected, distance, impulse response; present sample calculations D‐D D‐T plasmas observed typical Nova TOF detectors. placement important minimizing yield below 1010 neutrons.