NASA Scientific and Technical Aerospace Reports
NASA Scientific and Technical Aerospace Reports
NASA Scientific and Technical Aerospace Reports
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20040047250 Lawrence Livermore National Lab., Livermore, CA<br />
Turbulence Simulations of X-point Physics on the L-H Transitions<br />
Xu, X. Q.; Cohen, R. H.; Nevins, W. M.; Porter, G. D.; Rensink, M. E.; Sep. 28, 2000; 18 pp.; In English<br />
Report No.(s): DE2004-15005849; UCRL-JC-137618; No Copyright; Avail: Department of Energy Information Bridge<br />
We show that the resistive X-point mode is dominant mode in boundary plasmas in X-point divertor geometry. The<br />
poloidal fluctuation phase velocity from the resistive X-point turbulence shows experimentally measured structure across<br />
separatrix. The fluctuation phase velocity is larger than E x B velocity both in L <strong>and</strong> H mode phases, by at least a factor of<br />
two. We also demonstrate that there is a strong poloidal asymmetry of particle flux in the proximity of the separatrix.<br />
Turbulence suppression in the L-H transition results when sources of energy <strong>and</strong> particles drive sufficient gradients as<br />
experiments.<br />
NTIS<br />
Turbulence; Diverters; Plasmas (Physics)<br />
20040047252 Lawrence Livermore National Lab., Livermore, CA<br />
Spheromak Formation Studies in SSPX<br />
Hill, D. N.; Bulmer, R. H.; Cohen, B. I.; Hooper, E. B.; LoDestro, L. L.; Sep. 29, 2000; 12 pp.; In English<br />
Report No.(s): DE2004-15005850; UCRL-JC-137828; No Copyright; Avail: Department of Energy Information Bridge<br />
We present results from the Sustained Spheromak Physics Experiment (SSPX) at LLNL, which has been built to study<br />
energy confinement in spheromak plasmas sustained for up to 2 ms by coaxial DC helicity injection. Peak toroidal currents<br />
as high as 600kA have been obtained in the 1m dia. (0.23m minor radius) device using injection currents between 200-400kA;<br />
these currents generate edge poloidal fields in the range of 0.2-0.4T. The internal field <strong>and</strong> current profiles are inferred from<br />
edge field measurements using the CORSICA code. Density <strong>and</strong> impurity control is obtained using baking, glow discharge<br />
cleansing, <strong>and</strong> titanium gettering, after which long plasma decay times ((tau)(ge) 1.5ms) are observed <strong>and</strong> impurity radiation<br />
losses are reduced from (approx.)50% to lesser than 20% of the input energy. Thomson scattering measurements show peaked<br />
electron temperature <strong>and</strong> pressure profiles with T(sub e) (0)(approx.)120eV <strong>and</strong> (beta)(sub e)(approx.)7%.<br />
NTIS<br />
Spheromaks; Electron Energy; Plasma Decay<br />
20040050167 Lawrence Livermore National Lab., Livermore, CA<br />
ECE Diagnostic of High Temperature ECRH Heated Plasmas on FTU<br />
Zerbini, M.; Buratti, P.; Tudisco, O.; Giruzzi, G.; Jan. 31, 2000; 20 pp.; In English<br />
Report No.(s): DE2004-15005771; UCRL-JC-142342; No Copyright; Avail: Department of Energy Information Bridge<br />
The Electron Cyclotron Emission (ECE) diagnostic on FTU tokamak is routinely performed with a Michelson<br />
interferometer with spectral range extending up to 1300 GHz. The diagnostic allowed accurate electron temperature<br />
measurements during the recent 140 Ghz Electron Cyclotron Resonance Heating (ECRH) experiments on FTU. Very accurate<br />
measurements have been performed on a wide range of electron temperatures <strong>and</strong> profile peaking. The ECE measurements<br />
have been compared with Thomson Scattering <strong>and</strong> with observations of X-ray spectra from highly stripped molybdenum ions.<br />
The suprathermal emission in these conditions has been studied.<br />
NTIS<br />
Tokamak Devices; Spectra<br />
20040050171 Lawrence Livermore National Lab., Livermore, CA<br />
WO21.3 Direct Drive Reentrant Cone Targets for Fast Ignition<br />
Stephens, R. B.; Nikroo, A.; Hill, D.; Smith, J. N.; Hatchett, S. P.; Aug. 23, 2003; 12 pp.; In English<br />
Report No.(s): DE2004-15005825; UCRL-JC-152045; No Copyright; Avail: Department of Energy Information Bridge<br />
Targets designed for fast ignition must have clear access for the ignitor laser to the compressed core. This is provided in<br />
current concepts by embedding a reentrant cone in the shell, the tip of the cone close to the center of the shell. We have<br />
designed a gas-tight direct-drive FI target as the first step in developing a FI ignition target, <strong>and</strong> have studied its implosion<br />
dynamics at Omega with back-lit <strong>and</strong> self-emission framing cameras. A step in the cone surface, <strong>and</strong> Al on the shell was<br />
required to make the assembly gas-tight; these assemblies withstood greater than 10 atm <strong>and</strong> had a typical pressure half-life<br />
of 2-6 hrs. The implosion of these targets was substantially different from that of previous indirect drive targets; there was<br />
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