APRIL 20, 2024 Report Micro-Quantification of Helium-3 and Helium-4 in TPBAR Components ( Read More )
APRIL 17, 2024 Conference Paper Progress in the Verification and Validation Efforts for START: A Spent Fuel Routing Tool ( Read More )
APRIL 17, 2024 Conference Paper A Comparison of As-loaded Dose Calculations to Measured Dose Rates ( Read More )
APRIL 11, 2024 Conference Paper Informing and Engaging the Future Workforce on Generation IV International Forum Reactor Systems ( Read More )
APRIL 11, 2024 Journal Article Standoff trace explosives vapor detection at meter distances ( Read More )
FEBRUARY 17, 2024 Journal Article Influence of processing on secondary phase formation and microstructural evolution at U-10Mo alloy and Zr interlayer interfaces ( Read More )
FEBRUARY 15, 2024 Journal Article Thermomechanical Properties of Neutron Irradiated Al3Hf-Al Thermal Neutron Absorber Materials ( Read More )
FEBRUARY 15, 2024 Report Evaluation of Oxygen Consumption as a Sensitive Measure of Electrical Cable Polymer Insulation Degradation ( Read More )
FEBRUARY 15, 2024 Book Chapter Radioxenon Detection for Monitoring Subsurface Nuclear Explosion ( Read More )
FEBRUARY 15, 2024 Conference Paper A Robust Processing Approach for Producing Highly Loaded Dispersion Fuels ( Read More )
FEBRUARY 15, 2024 Conference Paper Forming Complex Nuclear Fuel Shapes in High-Loaded Silicide Surrogates ( Read More )
FEBRUARY 15, 2024 Report Capability to Process and Characterize Uranium-Zirconium (U-Zr) and Uranium-Zirconium-Plutonium (U-Zr-Pu) Alloys ( Read More )
FEBRUARY 15, 2024 Journal Article Neptunium redox speciation and determination of its total concentration in dissolved fuel simulant solutions by spectrophotometry ( Read More )
FEBRUARY 15, 2024 Journal Article Impacts of Future Nuclear Power Generation on the International Monitoring System ( Read More )
FEBRUARY 15, 2024 Report Lead-Bismuth Small Modular Reactor (SMR) Licensing Development - CRADA 371 (Abstract) ( Read More )
FEBRUARY 15, 2024 Report RFA-17-14597, Methodology for Meeting Containment System Principal Design Criteria to Maximize the Passive Safety Value in Advanced Nuclear Energy Economic Competitiveness - CRADA 397 (Abstract) ( Read More )