Call Number (LC) Title Results
E 1.99:inl/con-08-14518 Analysis on the Density Driven Air-Ingress Accident in VHTRs 1
E 1.99:inl/con-08-14519 Stress and Heat Transfer Analyses for Different Channel Arrangements of PCHE 1
E 1.99:inl/con-08-14522 Plasma Synthesis of Nanoparticles for Nanocomposite Energy Applications 1
E 1.99:inl/con-08-14524 An Innovative Hybrid Loop-Pool SFR Design and Safety Analysis Methods Today and Tomorrow. 1
E 1.99:inl/con-08-14527 Advanced Test Reactor -- Testing Capabilities and Plans AND Advanced Test Reactor National Scientific User Facility -- Partnerships and Networks 1
E 1.99:inl/con-08-14533 Comparison of HEU and LEU Fuel Neutron Spectrum for ATR Fuel Element and ATR Flux-Trap Positions 1
E 1.99:inl/con-08-14535 Common-Cause Failure Analysis in Event Assessment 1
E 1.99:inl/con-08-14536 Practical Issues in Component Aging Analysis 1
E 1.99:inl/con-08-14541 A Global Approach to the Physics Validation of Simulation Codes for Future Nuclear Systems 1
E 1.99:inl/con-08-14550 MONOLITHIC FUEL FABRICATION PROCESS DEVELOPMENT AT THE IDAHO NATIONAL LABORATORY 1
E 1.99:inl/con-08-14551 TESTING AND ACCEPTANCE OF FUEL PLATES FOR RERTR FUEL DEVELOPMENT EXPERIMENTS 1
E 1.99:inl/con-08-14569 Fresh Fuel Characterization of U-Mo Alloys 1
E 1.99:inl/con-08-14592 Research on Spent Fuel Storage and Transportation in CRIEPI (Part 2 Concrete Cask Storage) 1
E 1.99:inl/con-08-14597 Finding Cryptography in Object Code 1
E 1.99:inl/con-08-14601 SYSTEM ANALYSIS OF NUCLEAR-ASSISTED SYNGAS PRODUCTION FROM COAL 1
E 1.99:inl/con-08-14612 Small-scale Specimen Testing of Monolithic U-Mo Fuel Foils 1
E 1.99:inl/con-08-14617 in situ Calcite Precipitation for Contaminant Immobilization 1
E 1.99:inl/con-08-14622 Idaho National Laboratory Experimental Research In High Temperature Electrolysis For Hydrogen And Syngas Production 1
E 1.99:inl/con-08-14623 A preliminary assessment of beryllium dust oxidation during a wet bypass accident in a fusion reactor 1
E 1.99:inl/con-08-14630 THE COMPONENT TEST FACILITY – A NATIONAL USER FACILITY FOR TESTING OF HIGH TEMPERATURE GAS-COOLED REACTOR (HTGR) COMPONENTS AND SYSTEMS 1