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A polar direct drive liquid deuterium–tritium wetted foam target concept for inertial confinement fusion
Author(s) -
Richard E. Olson,
Mark J. Schmitt,
Brian Haines,
G. E. Kemp,
C. B. Yeamans,
B. E. Blue,
D. W. Schmidt,
A. Haid,
M. Farrell,
Paul A. Bradley,
H. F. Robey,
R. J. Leeper
Publication year - 2021
Publication title -
physics of plasmas
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.75
H-Index - 160
eISSN - 1089-7674
pISSN - 1070-664X
DOI - 10.1063/5.0062590
Subject(s) - thermonuclear fusion , national ignition facility , inertial confinement fusion , ignition system , physics , deuterium , nuclear engineering , tritium , plasma , nuclear physics , polar , fusion power , thermodynamics , engineering , astronomy

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