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Title: Status of Indirect Drive ICF Experiments on the National Ignition Facility

In the quest to demonstrate Inertial Confinement Fusion (ICF) ignition of deuterium-tritium (DT) filled capsules and propagating thermonuclear burn with net energy gain (fusion energy/laser energy >1), recent experiments on the National Ignition Facility (NIF) have shown progress towards increasing capsule hot spot temperature (Tion>5 keV) and fusion neutron yield (~1016), while achieving ~2x yield amplification by alpha particle deposition. At the same time a performance cliff was reached, resulting in lower fusion yields than expected as the implosion velocity was increased. Ongoing studies of the hohlraum and capsule physics are attempting to disseminate possible causes for this performance ceiling.
Authors:
 [1]
  1. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
Publication Date:
OSTI Identifier:
1248275
Report Number(s):
LLNL--TR-686482
TRN: US1601263
DOE Contract Number:
AC52-07NA27344
Resource Type:
Technical Report
Research Org:
Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
Sponsoring Org:
USDOE
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; FUSION YIELD; GAIN; US NATIONAL IGNITION FACILITY; D-T OPERATION; NEUTRONS; TRITIUM; ALPHA PARTICLES; INERTIAL CONFINEMENT; DEUTERIUM; INDIRECT DRIVE ICF; KEV RANGE; NET ENERGY; PERFORMANCE; HOT SPOTS; AUGMENTATION; DEPOSITION; THERMONUCLEAR IGNITION; IMPLOSIONS; VELOCITY; RESEARCH PROGRAMS