Call Number (LC) Title Results
E 1.99:conf-860601-1 Nuclear power options viability Oak Ridge National Laboratory's study. 1
E 1.99:conf-860601-2 The ultimate safe (US) Reactor A concept for the third millenium. 1
E 1.99: conf-860601-3 Parametric economic studies for inertial confinement fusion electric power plants 1
E 1.99: conf-860601-4 MINIMARS a 600-MWe advanced mirror-fusion reactor design. 1
E 1.99: conf-860601-5 Fusion breeder blanket nucleonics 1
E 1.99: conf-860601-6 Production of muons for fusion catalysis in a magnetic mirror configuration 1
E 1.99: conf-860601-6-rev.1 Production of muons for fusion catalysis in a magnetic mirror configuration. Revision 1 1
E 1.99: conf-860601-7 Muon sticking factor in muon catalyzed fusion and the other aspect of this fusion process 1
E 1.99: conf-860601-8 Compact nuclear power systems based on particle bed reactors 1
E 1.99: conf-860601-9 Inertial fusion research at Lawrence Livermore National Laboratory program status and future applications. 1
E 1.99: conf-860601-10 Compact Torus plasma ring accelerator a new type driver for inertial confinement fusion. 1
E 1.99: conf-860601-11-rev.1 Emerging nuclear energy systems Economic challenge. 1
E 1.99: conf-860601-12 Recent progress in heavy-ion fusion in the US 1
E 1.99:conf-860602-3 Magnetic susceptibility of CfCl₃ and its dependence on crystal structure. [CfCl₃] 1
E 1.99: conf-860602-4 Stabilization of actinides and lanthanides in unusually high oxidation states 1
E 1.99:conf-860602-6 ⁵⁷Fe Mossbauer spectroscopy of U₆Fe 1
E 1.99:conf-860603-1 Head-end and solvent extraction studies using fast-flux test facility fuel 1
E 1.99:conf-860603-2 Acid-split flowsheets for uranium-plutonium partitioning without a reductant 1
E 1.99: conf-860603-4 Regeneration and recycle of spent oxide reduction solvent salts used in pyrochemical plutonium recovery operations at Los Alamos 1
E 1.99: conf-860603-5 Prospects for improved fusion reactors 1