Status of Indirect Drive ICF Experiments on the National Ignition Facility

Dewald, E.¹ 

[1]Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

关键词: 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;   

DOI  :  10.2172/1248275
RP-ID  :  LLNL--TR-686482
PID  :  OSTI ID: 1248275
Others  :  TRN: US1601263

学科分类：原子、分子光学和等离子物理

美国|英语

来源: SciTech Connect

【 摘 要 】

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 (T_ion>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.