DC CICC retrofit magnet preliminary design, software development and analysis report

The January 1992 quarterly progress report discusses a two-dimensional finite element analysis (FEA) of the proposed retrofit MHD coil. The superconducting Cable-in-Conduit Conductor (CICC) winding pack has a smooth, semi-elliptical cross section and is supported by a similarly shaped strap which resists the electromagnetic forces tending to separate the coils on each side of the channel. The coils are designed to produce a peak on-axis field of 4.5 tesla with a nominal current density of 13.05{times}10{sup 6} A/m{sup 2}. A sketch of the magnet system and structure is shown in Fig. 1.0-1. The objective of this analysis is to quantify the highly 3-D characteristics of the proposed superconductivity magnet system, and develop an appropriate support concept. A fully paramatized 3-D finite element model of the coil and structure is developed as a means of obtaining the field and stress solutions. The flexibility of FEA and a model built using design parameters allows variations in the coil end turn bend radius, strap thickness, support details and positions to be studied. The preliminary results show the calculated stresses as a result of this iterative design process

DC CICC retrofit magnet preliminary design, software development and analysis report

The January 1992 quarterly progress report discusses a two-dimensional finite element analysis (FEA) of the proposed retrofit MHD coil. The superconducting Cable-in-Conduit Conductor (CICC) winding pack has a smooth, semi-elliptical cross section and is supported by a similarly shaped strap which resists the electromagnetic forces tending to separate the coils on each side of the channel. The coils are designed to produce a peak on-axis field of 4.5 tesla with a nominal current density of 13.05{times}10{sup 6} A/m{sup 2}. A sketch of the magnet system and structure is shown in Fig. 1.0-1. The objective of this analysis is to quantify the highly 3-D characteristics of the proposed superconductivity magnet system, and develop an appropriate support concept. A fully paramatized 3-D finite element model of the coil and structure is developed as a means of obtaining the field and stress solutions. The flexibility of FEA and a model built using design parameters allows variations in the coil end turn bend radius, strap thickness, support details and positions to be studied. The preliminary results show the calculated stresses as a result of this iterative design process

Progress in direct-drive inertial confinement fusion research at the laboratory for laser energetics

Direct-drive inertial confinement fusion (ICF) is expected to demonstrate high gain on the National Ignition Facility (NIF) in the next decade and is a leading candidate for inertial fusion energy production. The demonstration of high areal densities in hydrodynamically scaled cryogenic DT or D$_{2}$ implosions with neutron yields that are a significant fraction of the “clean” 1-D predictions will validate the ignition-equivalent direct-drive target performance on the OMEGA laser at the Laboratory for Laser Energetics (LLE). This paper highlights some of the recent experimental and theoretical progress toward this validation.
The NIF will initially be configured for x-ray drive and with no beams placed at the target equator to provide a symmetric irradiation of a direct-drive capsule. LLE is developing the “polar-direct-drive” (PDD) approach that repoints beams toward the target equator. Initial 2-D simulations have shown ignition. 
LLE is currently constructing the multibeam, 2.6-kJ/beam, petawatt laser system OMEGA EP. Integrated fast-ignition experiments, combining the OMEGA EP and OMEGA laser systems, will begin in FY08