Measurement of ICF fuel ion temperature on Nova

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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 … continued below

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7 p.

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Harris, D. B. & Chrien, R. E. February 1, 1994.

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This article is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by the UNT Libraries Government Documents Department to the UNT Digital Library, a digital repository hosted by the UNT Libraries. It has been viewed 11 times. More information about this article can be viewed below.

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Description

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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7 p.

Notes

OSTI as DE94006150; Paper copy available at OSTI: phone, 865-576-8401, or email, reports@adonis.osti.gov

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  • 11. international workshop on laser interaction and related plasma phenomena,Monterey, CA (United States),25-29 Oct 1993

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  • Other: DE94006150
  • Report No.: LA-UR--94-345
  • Report No.: CONF-931048--11
  • Grant Number: W-7405-ENG-36
  • Office of Scientific & Technical Information Report Number: 10129918
  • Archival Resource Key: ark:/67531/metadc1319355

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

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  • February 1, 1994

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  • Nov. 3, 2018, 11:47 a.m.

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  • Nov. 13, 2018, 1:20 p.m.

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Harris, D. B. & Chrien, R. E. Measurement of ICF fuel ion temperature on Nova, article, February 1, 1994; New Mexico. (https://digital.library.unt.edu/ark:/67531/metadc1319355/: accessed July 29, 2021), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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