Call Number (LC) Title Results
E 1.99: conf-840913-7 Sodium concrete reaction structural considerations. 1
E 1.99: conf-840913-8 Behavior of reinforced concrete at elevated temperatures 1
E 1.99: conf-840914-1 TRAC-PF1 analyses of potential pressurized-thermal-shock transients at a Combustion-Engineering PWR. [Overcooling] 1
E 1.99:conf-840914-2 Calculation of the limiting CESSAR feedwater line break transient 1
E 1.99: conf-840914-3 Quench cooling of superheated debris beds in containment during LWR core meltdown accidents 1
E 1.99: conf-840914-3-rev Quench cooling of superheated debris beds in containment during LWR core meltdown accidents 1
E 1.99: conf-840914-5 Multivent effects in a large scale boiling water reactor pressure suppression system 1
E 1.99: conf-840914-10 Seismic risk assessment as applied to the Zion Nuclear Generating Station 1
E 1.99:conf-840914-13 Results and analysis of reactor-material experiments on ex-vessel corium quench and dispersal 1
E 1.99: conf-840914-14 Logic flowgraph model for disturbance analysis of a PWR pressurizer system 1
E 1.99: conf-840914-17 Transient moisture migration in concrete during severe reactor accidents 1
E 1.99:conf-840914-28 Measurement and characterization of fission products released from LWR fuel 1
E 1.99: conf-840915-1 Long-pulse beamlines for the mirror fusion test facility 1
E 1.99: conf-840915-2 Performance of the Cascade inertial-confinement-fusion conceptual reactor 1
E 1.99: conf-840915-4 Magnetic divertor design for the compact reversed-field pinch reactor 1
E 1.99:conf-840915-6 Startup of Large Coil Test Facility 1
E 1.99: conf-840915-7 Comparison of three ICF reactor designs 1
E 1.99:conf-840915-9 All solid state high voltage power supply for neutral beam sources 1
E 1.99: conf-840915-10 Diagnostics for the NBETF actively cooled beamdump 1
E 1.99:conf-840916-3-draft Remote handling requirements and considerations for D-T fusion reactors 1