| Development of Irradiation Test Devices for Transient Testing |
6 |
| Experimentally Known Properties of U-10Zr Alloys: A Critical Review |
6 |
| Thermophysical Properties of Molten Stainless Steel Containing 5 mass % B4C |
5 |
| Transient Reactor Test (TREAT) Facility Design and Experiment Capability |
5 |
| Variable and Assured Peak Electricity Production from Base-Load Light-Water Reactors with Heat Storage and Auxiliary Combustible Fuels |
5 |
| Methodological and Practical Comparison of Integrated Probabilistic Risk Assessment (I-PRA) with the Existing Fire PRA of Nuclear Power Plants |
5 |
| Development of a Pragmatic Approach to Model Input Uncertainty Quantification for BEPU Applications |
4 |
| TREAT Restart Project |
4 |
| Technology, Policy, and Market Drivers of (and Barriers to) Advanced Nuclear Reactor Deployment in the United States After 2030 |
4 |
| A Critical Review of the Experimentally Known Properties of U-Pu-Zr Alloys. Part 1: Phases and Phase Diagrams |
4 |
| Simulations of Pressure-Tube-Heavy-Water Reactor Cores Fueled with Thorium-Based Mixed-Oxide Fuels |
4 |
| Development of a Validation Approach for an Integrated Waste Glass Melter Model |
4 |
| FHR, HTGR, and MSR Pebble-Bed Reactors with Multiple Pebble Sizes for Fuel Management and Coolant Cleanup |
3 |
| Eye-Tracking Studies Based on Attentional-Resource Effectiveness and Insights into Future Research |
3 |
| Design and Operation of a Sensible Heat Peaking Unit for Small Modular Reactors |
3 |
| Investigations on Detecting Potential Nuclear Material Diversion from a Pyroprocessing Facility |
3 |
| A Scoping Study of the Chemical Behavior of Cesium Iodide in the Presence of Boron in the Condensed Phase (650 degrees C and 400 degrees C) Under Primary Circuit Conditions |
3 |
| Steady-State Subchannel Thermal-Hydraulic Assessment of Proposed Thorium Fuel Designs |
3 |
| Numerical Study of Integral Inherently Safe Light Water Reactor in Case of Inadvertent DHR Operation Based on the Multiscale Method |
3 |
| Fluoride-Salt-Cooled High-Temperature Test Reactor Thermal-Hydraulic Licensing and Uncertainty Propagation Analysis |
3 |
| Fabrication of ZrN Barrier Coatings for U-Mo Microspheres Via Fluidized Bed Chemical Vapor Deposition Using a Metalorganic Precursor |
3 |
| Thermal Energy Storage Configurations for Small Modular Reactor Load Shedding |
3 |
| Use of Dynamic Event Trees and Deep Learning for Real-Time Emergency Planning in Power Plant Operation |
3 |
| Development of Advanced Instrumentation for Transient Testing |
3 |
| Transient Reactor Test Facility Advanced Transient Shapes |
3 |
| Restart of the Transient Reactor Test (TREAT) Facility Neutron Radiography Program |
3 |
| Safety Strategy and Update of the TREAT Facility Safety Basis |
3 |
| Multiscaled Experimental Investigations of Corrosion and Precipitation Processes After Loss-of-Coolant Accidents in Pressurized Water Reactors |
3 |
| High-Resolution Velocity Field Measurements of Turbulent Round Free Jets in Uniform Environments |
3 |
| Measurement of Type 304L Stainless Steel and 16MND5 Ferritic Steel Density and Surface Tension: Possible Impact for Stratified Molten Pool |
3 |
| Advanced Methodology for Uncertainty Propagation in Computer Experiments with Large Number of Inputs |
3 |
| High-Fidelity Simulation of Flow-Induced Vibrations in Helical Steam Generators for Small Modular Reactors |
3 |
| Nuclear Forensics Methodology for Reactor-Type Attribution of Chemically Separated Plutonium |
3 |
| Measurements of Total Hemispherical Emissivity of A508/A533B Alloy Steel |
2 |
| A Second Generation Multiphase-CFD Framework Toward Predictive Modeling of DNB |
2 |
| Evaluation of the PAR Mitigation System in Swiss PWR Containment Using the GOTHIC Code |
2 |
| Application of the Improved Spacer Grid Model in Subchannel Analysis Code |
2 |
| Transient Reactor Test (TREAT) Facility Restart Heat Balance Calibration and Rod Worth Measurements |
2 |
| Transient Reactor Test (TREAT) Facility Initial Approach to Restart Criticality Following Extended Standby Operation |
2 |
| Metrology for Transient Reactor Characterization Using Uranium Wires |
2 |
| Analysis of Core Characterization Transients for TREAT Restart |
2 |
| Development of an Experimental Routine for Electrochemical and Laser-Induced Breakdown Spectroscopy Composition Measurements of SmCl3 in LiCl-KCl Eutectic Salt Systems |
2 |
| Using Kernel Density Estimation to Detect Loss-of-Coolant Accidents in a Pressurized Water Reactor |
2 |
| Dynamic Modeling and Performance Analysis of a Two-Fluid Molten-Salt Breeder Reactor System |
2 |
| Response Matrix Method-Based Importance Solver and Variance Reduction Scheme in the Serpent 2 Monte Carlo Code |
2 |
| Development of the Tritium Transport Analysis Code for the Thorium-Based Molten Salt Reactor |
2 |
| Verification of Modelica-Based Models with Analytical Solutions for Tritium Diffusion |
2 |
| ATR Compendium: Irradiation Test Capabilities |
2 |
| Tritium Transport Analysis in a 2-MW Liquid-Fueled Molten Salt Experimental Reactor with the Code TMSR-TTAC |
2 |
| Ab-Initio Calculation of Spectral Absorption Coefficients in Molten Fluoride Salts with Metal Impurities |
2 |
