Cryogenic DT and D2 targets for inertial confinement fusion
National Ignition Facility
Cryogenics
Nova (rocket)
Fusion power
DOI:
10.1063/1.2671844
Publication Date:
2007-04-26T22:03:22Z
AUTHORS (38)
ABSTRACT
Ignition target designs for inertial confinement fusion on the National Facility (NIF) [W. J. Hogan , Nucl. Fusion41, 567 (2001)] are based a spherical ablator containing solid, cryogenic-fuel layer of deuterium and tritium. The need solid-fuel layers was recognized more than 30 years ago considerable effort has resulted in production cryogenic targets that meet most critical fabrication tolerances ignition NIF. At University Rochester’s Laboratory Laser Energetics (LLE), inner-ice surface DT capsules formed using β-layering meets surface-smoothness requirement (<1-μm rms all modes). Prototype x-ray-drive being produced at Lawrence Livermore nearing required LLE, these (and D2) imploded direct-drive 60-beam, 30-kJ UV OMEGA laser [T. R. Boehly Opt. Commun.133, 495 (1997)]. energy scaled from baseline direct-drive-ignition design Significant progress with formation characterization both direct x-ray drive will be described. Results recent implosions also presented.
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