Call Number (LC) Title Results
E 1.99:ornl/tm-2000/165 Ethanol Demand in United States Production of Oxygenate-limited Gasoline
Ethanol Demand in United States Regional Production of Oxygenate-limited Gasoline 		2
E 1.99:ornl/tm-2000/172 Dual Mode Inverter Control Test Verification 1
E 1.99:ornl/tm-2000/173 Further Investigations of NIST Water Sphere Discrepancies 1
E 1.99:ornl/tm-2000/174 Oak Ridge National Laboratory Facilities Revitalization Project - Project Management Plan 1
E 1.99:ornl/tm-2000/180 VENUS-2 MOX Core Benchmark Results of ORNL Calculations Using HELIOS-1.4. 1
E 1.99:ornl/tm-2000/180/r1 VENUS-2 MOX Core Benchmark Results of ORNL Calculations Using HELIOS-1.4 - Revised Report. 1
E 1.99:ornl/tm-2000/181 Impacts of Venturi Turbulent Mixing on the Size Distributions of Sodium Chloride and Dioctyl-Phthalate Aerosols
Impacts of Venturi Turbulent Mixing on the Size Distribution of Sodium Chloride and Dioctyl-Phthalate Aerosols 		2
E 1.99:ornl/tm-2000/184 An Evaluation of a Dual Coriolis Meter System for In-Line Monitoring of Suspended Solids Concentrations in Radioactive Slurries 2
E 1.99:ornl/tm-2000/186 Wastewater Triad Project Solid-Liquid Separator FY 2000 Deployment. 1
E 1.99:ornl/tm-2000/191 Ultra-Clean Diesel Fuel U.S. Production and Distribution Capability. 1
E 1.99:ornl/tm-2000/193 Method to Correlate CFD Discriminator Level and Energy Deposition by Neutrons and Photons in a Fast Plastic Scintillating Detector 1
E 1.99:ornl/tm-2000/195 Effect of Surface Condition and Heat Treatment on Corrosion of Type 316L Stainless Steel in a Mercury Thermal Convection Loop 2
E 1.99:ornl/tm-2000/200 SURFING A Program for Precise Determination of Sample Position in Stress Measurements Via Neutron Diffraction. 1
E 1.99:ornl/tm-2000/202 FY 2000 Saltcake Dissolution and Feed Stability Workshop 1
E 1.99:ornl/tm-2000/204 Revision of the MCSAP Allocation Formula Summary Report. 2
E 1.99:ornl/tm-2000/208 Quickest Paths for Different Network Router Mechanisms 2
E 1.99:ornl/tm-2000/212 R-Matrix Evaluation of 16O Neutron Cross Sections up to 6.3 MeV
R-Matrix Evaluation of ¹⁶O neutron cross sections up to 6.3 MeV 		2
E 1.99:ornl/tm--2000/222 Fabrication of a Sludge-Conditioning System for Processing Legacy Wastes from the Gunite and Associated Tanks 1
E 1.99:ornl/tm-2000/222 Fabrication of a Sludge-Conditioning System for Processing Legacy Wastes from the Gunite and Associated Tanks 1
E 1.99:ornl/tm-2000/230 A Critical Review of Practice of Equating the Reactivity of Spent Fuel to Fresh Fuel in Burnup Credit Criticality Safety Analyses for PWR Spent Fuel Pool Storage 1