| Call Number (LC) | Title | Results |
|---|---|---|
| E 1.99:ornl/tm--1999/283 | Status and needs for tank isolation system contingencies at the Oak Ridge National Laboratory | 1 |
| E 1.99:ornl/tm-1999/283 | Status and Needs for Tank Isolation System Contingencies at the Oak Ridge National Laboratory | 1 |
| E 1.99:ornl/tm-1999/284 | KENO3D Visualization Tool for KENO V.a and KENO-VI Geometry Models | 1 |
| E 1.99:ornl/tm-1999/287 | Systems Requirement Document for the MSRE U-233 Conversion System | 1 |
| E 1.99:ornl/tm-1999/287/r1 | System Requirements Document for the Molten Salt Reactor Experiment | 1 |
| E 1.99:ORNL/TM-1999/288 | Review of Subcritical Source-Driven Noise Analysis Measurements | 1 |
| E 1.99:ornl/tm-1999/288 | Review of Subcritical Source-Driven Noise Analysis Measurements | 1 |
| E 1.99:ornl/tm-1999/292 | VOLVOF An update of the CFD code, SOLA-VOF. | 1 |
| E 1.99:ornl/tm-1999/299 |
Neutronics Benchmarks of Mixed-Oxide Fuels using the SCALE/CENTRM Sequence Neutronics benchmarks of mixed-oxide fuels using the SCALE/CENTRM sequence |
2 |
| E 1.99:ORNL/TM-1999/300 | Evaluation of prompt fission gamma rays for use in simulating nuclear safeguard measurements | 1 |
| E 1.99:ORNL/TM--1999/302 | Brief summary of unreflected and unmoderated cylindrical critical experiments with oralloy at Oak Ridge | 1 |
| E 1.99:ornl/tm-1999/302 | Brief Summary of Unreflected and Unmoderated Cylindrical Critical Experiments with Oralloy at Oak Ridge | 1 |
| E 1.99:ornl/tm-1999/303 | Review and Prioritization of Technical Issues Related to Burnup Credit for LWR Fuel | 1 |
| E 1.99:ornl/tm-1999/304 | Quarterly Progress Report for the Chemical and Energy Research Section of the Chemical Technology Division July-September 1999. | 1 |
| E 1.99:ornl/tm--1999/312 | Measurement of achievable plutonium decontamination from gallium by means of PUREX solvent extraction | 1 |
| E 1.99:ornl/tm-1999/318 | Compilation of Requirements for Safe Handling of Fluorine and Fluorine-Containing Products of Uranium Hexafluoride Conversion | 1 |
| E 1.99:ORNL/TM--1999/320 | Application of stochastic and artificial intelligence methods for nuclear material identification | 1 |
| E 1.99:ornl/tm-1999/322 | Experience With the SCALE Criticality Safety Cross Section Libraries | 1 |
| E 1.99:ORNL/TM-1999/323 | Corrosion of alloy 718 in a mercury thermal convection loop | 1 |
| E 1.99:ornl/tm-1999/325 | Feasibility of High Resolution P- and S-Wave Seismic Reflection to Detect Methane Hydrate | 1 |
