Call Number (LC) Title Results
E 1.99:ornl/tm-2009/287 Assessment of Cavitation-Erosion Resistance of 316LN Stainless Steel Following a Nitro-Carburizing Surface Treatment 1
E 1.99:ornl/tm-2009/288 Calculation Package Derivation of Facility-Specific Derived Air Concentration (DAC) Values in Support of Spallation Neutron Source Operations. 1
E 1.99:ornl/tm-2009/292 Health Effects from Advanced Combustion and Fuel Technologies 1
E 1.99:ornl/tm-2009/293 Hydraulic Permeability of Resorcinol-Formaldehyde Resin 1
E 1.99:ornl/tm-2009/297 An Analysis of Testing Requirements for Fluoride Salt Cooled High Temperature Reactor Components 1
E 1.99:ornl/tm-2009/302 Diversity Strategies for Nuclear Power Plant Instrumentation and Control Systems 1
E 1.99:ornl/tm-2009/303 Linux OS Jitter Measurements at Large Node Counts using a BlueGene/L 1
E 1.99:ornl/tm-2009/304 Data Compilation for AGR-2 UCO Variant Compact Lot LEU06-OP1-Z 1
E 1.99:ornl/tm-2009/305 Data Compilation for AGR-2 UCO Baseline Compact Lot LEU07-OP1-Z 1
E 1.99:ornl/tm-2009/308 PREPARING FOR EXASCALE ORNL Leadership Computing Application Requirements and Strategy. 1
E 1.99:ornl/tm-2009/310 Streamlining Transportation Corridor Planning Processess Freight and Traffic Information. 1
E 1.99:ornl/tm-2009/311 Establishing a Cost Basis for Converting the High Flux Isotope Reactor from High Enriched to Low Enriched Uranium Fuel 1
E 1.99:ornl/tm-2009/313 Design Study for a Low-Enriched Uranium Core for the High Flux Isotope Reactor, Annual report for FY 2009 1
E 1.99:ornl/tm-2009/314 Energy Assurance Essential Energy Technologies for Climate Protection and Energy Security. 1
E 1.99:ornl/tm-2009/321 Analysis of Experimental Data for High Burnup PWR Spent Fuel Isotopic Validation - Vandellos II Reactor 1
E 1.99:ornl/tm-2009/322 FY 2009 Annual Report of Joule Software Metric SC GG 3.1/2.5.2, Improve Computational Science Capabilities 1
E 1.99:ornl/tm-2009/324 Fabrication and Characterization of Sixteen SiC Variants Deposited on the Same IPyC Substrate for Fracture Strength Testing 1
E 1.99:ornl-tm--2010 COMPATIBILITY OF DISPERSION STRENGTHENED ALUMINUM WITH URANIUM MONOCARBIDE. 1
E 1.99:ornl/tm-2010/6 Evaluation of Activity Concentration Values and Doses due to the Transport of Low Level Radioactive Material 1
E 1.99:ornl/tm-2010/7 Review of Sorghum Production Practices Applications for Bioenergy. 1