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Title: Investigating inertial confinement fusion target fuel conditions through x-ray spectroscopy

Journal Article · · Physics of Plasmas
DOI:https://doi.org/10.1063/1.3694246· OSTI ID:22072416
 [1]
  1. Sandia National Laboratories, Albuquerque, New Mexico 87185 (United States)

Inertial confinement fusion (ICF) targets are designed to produce hot, dense fuel in a neutron-producing core that is surrounded by a shell of compressing material. The x-rays emitted from ICF plasmas can be analyzed to reveal details of the temperatures, densities, gradients, velocities, and mix characteristics of ICF targets. Such diagnostics are critical to understand the target performance and to improve the predictive power of simulation codes.

OSTI ID:
22072416
Journal Information:
Physics of Plasmas, Vol. 19, Issue 5; Other Information: (c) 2012 American Institute of Physics; Country of input: International Atomic Energy Agency (IAEA); ISSN 1070-664X
Country of Publication:
United States
Language:
English

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