Measurement of ICF fuel ion temperature on Nova
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.
- Research Organization:
- Los Alamos National Lab., NM (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 10129918
- Report Number(s):
- LA-UR-94-345; CONF-931048-11; ON: DE94006150
- Resource Relation:
- Conference: 11. international workshop on laser interaction and related plasma phenomena,Monterey, CA (United States),25-29 Oct 1993; Other Information: PBD: [1994]
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
ICF DEVICES
PLASMA DIAGNOSTICS
INERTIAL CONFINEMENT
ION TEMPERATURE
TIME-OF-FLIGHT METHOD
LASER FUSION REACTORS
NOVA FACILITY
DEUTERIUM TARGET
LASER-PRODUCED PLASMA
NEUTRON SPECTROSCOPY
700411
700320
INERTIAL CONFINEMENT DEVICES
PLASMA DIAGNOSTIC TECHNIQUES AND INSTRUMENTATION