Nuclear Technology

Article	Citations
Validation of Pronghorn Pressure Drop Correlations Against Pebble Bed Experiments	54
Thermal-Hydraulic Core Design of a Thorium-Based Molten Salt Fast Energy Amplifier	31
Mapping the Hydrogen Economy in Ghana: The Strategic Contribution of Small Modular Reactors	21
Neutronics and Thermo-Fluids Simulation of Generic Pebble-Bed Fluoride-Salt-Cooled High-Temperature Reactor	20
STORAGE: A Source Term Model for Intermediate-Level Radioactive Waste	19
Comprehensive Study on p-n Junction and Schottky Barrier Betavoltaic Battery with 14 C Beta-Emitting Source	18
Availability of Critical Benchmark Experiments for the Pebble Tanker Transportation Model for Nuclear Criticality Safety Validation of TRISO Pebbles	18
Code Validation of SAM Using Forced and Natural Circulation Data from NACIE-UP Benchmark	17
An Anisotropic Neutron Collimating System for Proton Accelerator-Generated Secondary Particles	17
Verification and Demonstration of One-Dimensional Freezing Model in SAM for Salt-Cooled Reactor Analysis Applications	16
Best Estimate Plus Uncertainty Analysis of Station Blackout Transient in Pool-Type Research Reactor	15
Spatiotemporal Evaluation of Bubble Characteristics in Sodium Using Real-Time X-Ray Imaging	15
Model Development for Thermal-Hydrology Simulations of a Full-Scale Heater Experiment in Opalinus Clay	15
Recent 238Pu Production Activities at Idaho National Laboratory	14
Risk Plus Some Attributes (R + SA): A New Risk-Informed Method for Prioritizing Inspection Activities During New Fuel Facility Construction	12
Nuclear Power Concepts and Development Strategies for High-Power Electric Propulsion Missions to Mars	12
Detection of Isotopes in Urban Source Search Low-Count Gamma Spectra Using Hopfield Neural Networks	11
Liquid Film Thickness for Gas-Liquid Annular Flow Across Grid Spacer with Vanes in Simple 3 × 3 Rod Bundle Channel	11
Enhancement of Fast Neutron Detection in Liquid Scintillator Detectors	11
Examination of Deep Learning Algorithm for Nuclear Proliferation Risk Modeling	11
A Framework for Event Detection in Nuclear Facilities Using Wireless Sensors and Actors Networks	10
Boiling and Drying Accident of High-Level Liquid Waste in a Reprocessing Plant: Measurement of the Liquid-Phase Mass Transfer Coefficients of NO 2 and RuO	10
Comparison of Two Methods for Obtaining the Variabilities in a FRAM Model of a Combined Nuclear Facility Project	10
Organic Telluride Formation from Paint Solvents Under Gamma Irradiation	10
Monte Carlo Analysis of Coolant Stream Impurity Gamma Emissions in Gas-Cooled Fast Reactors	10

Fluid Dynamics Effects of a Porous Blockage on Laminar Flow in the Interior Subchannels of a 61-Pin Wire-Wrapped Rod Bundle	9
Revisiting Mobile Paste Reactor Fuel	9
Research on Active Disturbance Rejection Control of Small Modular Reactor Once-Through Steam Generator Based on Differential Evolution Optimization Algorithm	9
Development of a Signal Processing Software for Scintillation Detectors and Implementation on an FPGA for Fast Sensing	9
Comparative Study of Raman and EPMA Elemental Mapping of an Unirradiated MOX Sample	9
Effect of Nb Addition on Corrosion Resistance of U-6Zr Alloys	9
Network Graph Laplacian-Based Sensor Projection in System-Level Modeling of Liquid-Metal Loop	8
Adaptive Model Predictive Control for Heat Pipe–Cooled Microreactors Under Normal and Heat Pipe Failure Conditions	8
The Use of High-Density UN Fuel in Heat-Pipe Microreactors	8
Highly Available Nuclear Power in a Microgrid Configuration for the ORNL Distribution System	8
Adsorption Properties of Cs(I) and Co(II) on GMZ Bentonite Colloids	8
Assessing the Structure-Based Turbulence Model Performance for Thermal Striping Applications Using Symmetric Jet Experiments	8
Comprehensive Study on Gamma-Ray, Neutron, and Charged Particle Shielding Properties of Glass Materials Using Analytical Methods and Monte Carlo Simulations	8
Thermal-Hydraulic Analysis of Inward and Outward Fuel Plate Buckling in a Typical MTR Reactor	8
A RELAP5-3D Model of the Lobo Lead Loop	7
CHF Enhancement by γ-Fe 2 O 3 Nanofluids with Pool Boiling Condition on a Downward-Facing Plane	7
Density Equation for Mixed Organic Solutions Containing tri- n -butyl Nitrate, n -Dodecane, Nitric Acid, and Nitrates of Heavy Metals	7
Development of Two-Step Method for Fast Chloride MSR Neutronics	7
A Structural Design Approach Tailored for the Rapid Preliminary Design of Microreactor Components	7
Pressure Drop Correlation Improvement for the Near-Wall Region of Pebble-Bed Reactors	7
Nuclear Reactor Operations Education and Training with Virtual Reality and an Immersive Desktop Application	7
Determination of Gain Scheduling Parameters for Loss of a Feedwater Pump Transient Mitigation Using Neural Networks	7
Development of Emergency Information System to Support Nuclear Power Plant Management in Severe Accident	6
Validation Matrix for Pool Scrubbing Models	6
Heat Transfer Analysis of Core Melt Contact with a CANDU Calandria	6
Validation of a Countercurrent Gas Flow Model for Use in the Kairos Power System Analysis Module (KP-SAM) Code	6
Evaluating Material Attractiveness of Minor Actinide Nuclear Fuel Intended for a Waste Transmutation Lead-Cooled Fast Reactor	6
Effect of Nozzle Diameter on Quenching Behavior of Simulant Material CaO-Fe2O3 Under Bottom Flooding Conditions	6
Development and Verification of Neutron Kinetics Parameter Calculation Program Applicable to Subcritical Systems of Long-Life Reactors	6
Direct Numerical Simulation and Large Eddy Simulation of a 67-Pebble-Bed Experiment	6
Safety Benefits Assessment for Accident Tolerant Fuels in Consideration of Steam Generator Tube Degradation Using Dynamic Event Tree Analysis	6
Study of the User Effect Impact in Forward Uncertainty Propagation Approaches Applied to Severe Accident	6
The Versatile Loop Facility: A New Infrastructure for Testing Components and Systems of Lead Fast Reactor Technology	6
Prognostics and Health Management for Maintenance-Dependent Processes	6
Sparse-View Neutron Computed Tomography 3-D Reconstruction via the Fast Gradient Projection Algorithm	6
A Multiwire Proportional Chamber for Standardization of Large-Area Sources: Methodology and Challenges for In-House Construction	5
Finely Divided Metal as Nuclear Reactor Fuel	5
Diagnostic Technique Characterizing Neutron Irradiation Effects on Additively Manufactured Inconel 625 Eliminating the Need for Remote Handling	5
Neutron Energy Spectrum Measurement and Unfolding Method Based on a Single Long Lithium- or Boron-Doped Scintillator	5
Sensitivity Analysis of Transient Critical Heat Flux by RIA Under High-Pressure Flow Boiling Conditions in TRTL	5
Mobile Application Development Plan for Fire Influence Analysis Using Algebraic Models	5
Radionuclide Transport in Channel Networks with Radial Diffusion in the Porous Rock Matrix	5
Prospects for Nuclear Microreactors: A Review of the Technology, Economics, and Regulatory Considerations	5
2D(r,θ) Simulations of the HBC-4 Power-to-Melt Experiment with the Fuel Performance Code ALCYONE	5
Systematic Component Investigation of the Steady-State High-Temperature In-Pile Nuclear Thermal Propulsion Experimental Test Bed	5
Rationally Designed Core-Shell Structured Fe 3 O 4 @NiFe-LDH Using MIL-100(Fe) as an Intermediate Linker for Efficient Uranium Ads	5
Multiphase Turbulence Modeling Using Sparse Regression and Gene Expression Programming	5
Acoustic Analysis of the Effects of Vapor-Liquid Interfacial Morphology on Pool-Boiling Heat Transfer	5
Build-to-Replace Strategy to Reduce Operations and Maintenance Costs for Advanced Reactors	5
Foreword: Special issue on the Nuclear Energy Advanced Modeling and Simulation Thermal Hydraulics Integrated Research Project	5

Assessment of Screen-Covered Grooved Sodium Heat Pipes for Microreactor Applications	5
Validation of a Hybrid Domain Overlapping Coupling Between SAM and CFD Against the TALL-3D Transients	5
Time-Dependent Experiment on Reactor Power Distribution Estimation by Ex-Core Detectors at UTR-KINKI	4
Clogging Properties of HEPA Filter Induced by Loading of Soot from Burned Glove-Box Panel Materials	4
Advancing Fixed-Source Reactor Analysis Through OpenNode Implementation	4
Exploring the Feasibility of Quantum-Based Secure Communications for Nuclear Applications	4
Analysis of AP1000 Small-Break Loss-of-Coolant Accident Using Reactor Transient Simulator	4
Nuclear Thermal-Hydraulic Phenomena: Bases and Challenges	4
A Way of Analyzing an Oxide Layer on Irradiated Plate-Type Atomized U-Mo Fuel Using an EPMA and X-Ray Image Mapping	4
Indirect Parameterized Risk Assessment Applied to Brazilian Nuclear Sector	4
The UO 2 Power-to-Melt Experiment Performed in the High Burnup Chemistry International Program	4
Discrete Element Method Simulation of the Idaho Calcine Simulant for Hot Isostatic Pressing Canister Filling Process: Part 2	4
Research on the Preliminary Prediction of Nuclear Core Design Based on Machine Learning	4
On the Development of a Novel Acoustic Flowmeter for High-Temperature Gas-Cooled Reactors	4
Constructing Neural Network Model to Evaluate and Predict Human Error Probability in Nuclear Power Plants Based on Eye Response, Workload Rating, and Situation Awareness	4
Equivalence of the Peierls and Serber Wartime Expressions for the Critical Radius of a Fissile Isotope	4
Remark About “Finely Divided Metal as Nuclear Reactor Fuel”	4
On the Symmetry of Blast Waves	4
Validation and Neutronic Analysis of the CENM TRIGA MARK II SCALE Research Reactor Model: Computations Versus Experiment	4
Preparation and Performance of a Self-Brittle Corrosive Bifunctional Detergent for Corrosive Deep Decontamination of Stainless Steel Surface Based on Controlled Polymerization by the RAFT One-Pot Meth	4
The Experimental and Simulation Results of LIVE-J2 Test—Investigation on Heat Transfer in a Solid–Liquid Mixture Pool	4
Numerical Simulation on Dispersion of Hydrogen Leaked in Particle Layers of Glass Beads and Soil	4
Modal Decomposition of the Flow in a Randomly Packed Pebble Bed with Direct Numerical Simulation	4
Path Toward a Breeding, Proliferation-Resistant, Thermal-Spectrum Molten Salt Reactor	4
Optimizing the Implementation of Small Modular Reactors into Ontario’s Future Energy Mix	4
Denoising Algorithm for Subtle Anomaly Detection	4
SCALE 6.2.4 Validation for Light Water Reactor Decay Heat Analysis	4
Comparison of Irradiated TRISO Fuel Radioactivity from Multiple Advanced Reactor Designs	4
Monte Carlo Perturbation Analysis of Fuel Temperature Variations in the MCNP Model of the Annular Core Research Reactor	4
Advanced Autonomous Welding for Refabrication and Follow-On Testing of Previously Irradiated Nuclear Fuel	4
Comment on Comparison Between Historic Nuclear Explosion Yield Formulas	4
Investigation of the Thermal Effects of MgO and ZnO Nanoparticles in a Pressurized Water Reactor Coolant with Computational Fluid Dynamics Model	4
Enhancing Site Evaluation Standards for Nuclear Power Plants in Indonesia: Human-Induced External Events	4
Neutronic Analysis of the Conceptual Molten Uranium Breeder Reactor Using MCNP and SCALE Tools	3
Integrating Econometrics and Artificial Intelligence to Assess the Impact of Trade on Nuclear Proliferation	3
Lead Fast Reactor Thermal-Hydraulic Testing Facilities in Support of the UK Advanced Modular Reactor Program	3
Experimental Validation of Modeling and Simulation Capabilities of RELAP5-TMSR with the NNCL Experimental Facility	3
Separation of Flux/Dose Contributions from Multiple Transport Pathways in Monte Carlo Shielding Analyses of a Consolidated Interim Spent Nuclear Fuel Storage Facility	3
Computational Framework for Estimating Cost of Equipment Disposal for Advanced Reactors	3
Numerical Investigation of Changes in Heat Transfer Coefficient of Water-Aluminum Oxide Nanofluid Cooling in Nuclear Reactors	3
Investigation of High-Temperature Compatibility of Select Oxides with Yttrium Hydride for Micro and Space Reactor Applications	3
Comparison of Neutron Radiation Response of Conventionally Wrought Versus Additive Manufacturing Production Methods in Alloy 625	3
Extrapolation of Monte Carlo–Derived Noble Gas Air-Submersion Effective Dose Rate Coefficients for Selected Occupational Settings to Other Geometries and Radionuclides	3
Separating Nuclear Reactors from the Power Block with Heat Storage to Improve Economics with Dispatchable Heat and Electricity	3
A Redundancy-Guided Approach for the Hazard Analysis of Digital Instrumentation and Control Systems in Advanced Nuclear Power Plants	3
Availability of the Emergency Safety Electrical System of a Konvoi Nuclear Power Plant Considering Mobile Arrangements of Diesel Generators After Fukushima	3
Study on Flow Characteristics of Integrated Natural Circulation Reactor Under Inclined Conditions	3
Determination of the Gas Plenum Temperature of the P2M Instrumented Fuel Rodlets on the Basis of a Thermal-Hydraulic Study of the Belgian Reactor 2 Pressurized Water Capsule	3
In Situ Chlorine Generation and Rare Earth Chlorination by Molten Salt Electrolysis	3
Experimental Performance Evaluation of Miniature Low-Area-Ratio Jet Pumps for High-Temperature Applications	3
Modeling of the P2M Past Fuel Melting Experiments with the Fuel Performance Code FAST-1.0.1	3
Safety Assessment Methodology for Transportation of Radioactive Material via Train	3
Analysis of Influence of Tube Failure on Performance of Passive Residual Heat Removal Heat Exchanger	3
Uncertainty-Aware and Explainable Human Error Detection in the Operation of Nuclear Power Plants	3
Design and Demonstration of an Additively Manufactured Integrated Pressure Limiting Structure for Insertion into a Nuclear Research Reactor	3
Neutronics Calculation Advances at Los Alamos: Manhattan Project to Monte Carlo	3
Presentation of the xM3 Test Case of the P2M Simulation Exercise and Modeling with the Fuel Performance Code ALCYONE	3
Uncertainty and Sensitivity Analyses for Postulated Severe Accidents of Reference PWRs and SMRs in the Frame of the IAEA CRP and Relevant Insights	3
Technical Reviewers	3
Canadian Contributions to the Manhattan Project and Early Nuclear Research	3
Impact of Steel Equipment on Cyclotron Activation and Its Implications for Radioactive Waste Management	3
Considerations for Hydride Moderator Readiness in Microreactors	3
Integral-Effect Test for Loss of Residual Heat Removal System During Mid-Loop Operation in ATLAS Facility	3
Evaluation of Reaction Rate Distribution Measurement in the Prototype Fast Reactor Monju	3
Application of FSVD Algorithm to Airborne Gamma Detection of Trace Radionuclides in the Process of a High Radon Background	3
Protected Loss-of-Flow Accident in a HLM Pool Facility: Long-Term Cooling Experiment	3
Multiphysics Analyses of the Bottom Components of the 3D Printed Transformational Challenge Reactor	3
Irregular, Backward-Compatible PWR Assembles with More Pins to Facilitate Uprates	3
Calculation of Isotope-Specific Fission Rates for Neutrino Source Calculation in PWR Fuel Diversion Safeguarding	3
Convolutional Neural Network–Aided Temperature Field Reconstruction: An Innovative Method for Advanced Reactor Monitoring	3
The Trinity High-Explosive Implosion System: The Foundation for Precision Explosive Applications	3
Lightweight Heat Pipe Radiator for Nuclear Reactor Power Systems on Lunar Surface	3
Processes and Interactions of Potential Relevance for Deep Geological Disposal of HLW and L/ILW at the Same Site—International Approaches and Transferability to the German Site Selection	3
Global Divergence in Nuclear Power Plant Construction: The Role of Political Decentralization	3
First Experimental Demonstration of the Use of a Novel Planar Segmented HPGe Detector for Gamma Emission Tomography of Mockup Fuel Rods	3
Commentary	3
A Study on Boiling Heat Transfer Performance of TiO 2 -CNTs Hybrid Nanofluid on a Downward-Facing Heating Surface	3
Application of Systems Usability Case in an Integrated System Validation of Control Room	3
Modeling of Lateral Flow in CFD for Subchannel Analysis	3
Correction	3

Parametric Analysis of Radiological Impact from Hypothetical Accident Scenario at the Sanmen Nuclear Power Plant	3
Verification of Uncertainty Distributions for Thermal-Hydraulic Mixing Parameters Used in KWU-MIX for Pressurized Thermal Shock	3
Advanced Reactor Control and Operations (ARCO): A University Research Facility for Developing Optimized Digital Control Rooms	3
Correlation Method of 3-D Detection of Distant Sources of Gamma Radiation and Neutrinos by Intensity Interferometry	3
Development of a Potential Facility Risk Index for Nuclear Safety and Security Using a Terrorism Scenario with a Hypothetical Nuclear Facility	2
Investigation and Analysis of Thermoelectrically Cooled CZT Performance	2
Numerical Simulations of Flow-Induced Deflections in MITR LEU Fuel Plate Due to Channel Size Disparity	2
Qualification of Metallic Fuel Data for Advanced SFR Applications	2
Startup and Multiphysics Analysis of a Compact kW-Class Thermal Spectrum Microreactor	2
Calculated Critical and Subcritical Data for Revision of ANSI/ANS 8.12	2
Hydride Transformations and Their Impact on Zirconium Alloy Cladding Embrittlement During Spent Nuclear Fuel Storage	2
Release Behavior of Gaseous Ruthenium Tetroxide During Heating of High-Level Liquid Waste Simulant During Simulated Accident Conditions	2
Lumped Parameter Analysis of Autogenous Propellant Pressurization System for Nuclear Thermal Rocket	2
Stability Tests and Analysis of a Low-Pressure Natural Circulation Loop with Flashing Instability	2
Bayesian Network–Based Fault Diagnostic System for Nuclear Power Plant Assets	2
i-LAMP: Global, Industrywide Learning Aging Management Program for Neutron-Absorber Materials in Spent Fuel Pools	2
Optimization of Elliptical U-Tube Heat Exchanger (EUTHE) for Spray Cooling Based on the Taguchi and CFD Method	2
Enhanced Video-Level Anomaly Feature Detection for Nuclear Power Plant Component Inspections Using the Latency Mechanism	2
Numerical Analysis of Heat Pipe Performance Considering Helium Gap Effects	2
Comments on the Physics of the Frisch-Peierls Memorandum	2
Assessment of Factory Fabrication Considerations for Nuclear Microreactors	2
Benchmarking Neutron Counting System for Passive Measurements and Active Interrogation of Unknown Objects for Fissile and Fissionable Materials Determination	2
Uncertainty Quantification for Multiphase Computational Fluid Dynamics Closure Relations with a Physics-Informed Bayesian Approach	2
Thermal Assessment of Repository Footprint Requirement for Advanced Fuel Cycles	2
Simulation and Mitigation of False Data Injection Cyberattacks on a Space Nuclear Reactor Power System	2
Electrochemical Identification of Metal Chlorides in Eutectic LiCl-KCl Without Prior Knowledge of Analyte Identities	2
Simplified Reactor Model for Microreactor Coupled with Helium Closed Brayton Cycle	2
Thermophysical Properties of a Uranium Nitride–Molybdenum-Tungsten Composite Fuel for Nuclear Thermal Propulsion	2
Void Fraction and Interfacial Friction in Vertical Circular Pipes with the Square Top End Under Flooding Conditions	2
A Batch Refueling Framework for Implementing the Sourdough Fuel Cycle and Waste Management Strategy in the EIRENE Novel Molten Salt Reactor Design	2
Design and Suitability Analysis of FPGA-Based TCP/IP Offload Module for Control Systems of FBRs	2
Identification of Carbon in Glassy Cesium-Bearing Microparticles Using Electron Microscopy and Formation Mechanisms of the Microparticles	2
Advancements in Yttrium Hydride Moderator Development	2
Digitalization, Management, and Synthesis of Thermal-Hydraulic Legacy Data Using the Dynamical System Scaling	2
Constitutive Modeling of Anisotropic Plasticity with ML Algorithms in Metals	2
A Risk Approach to the Management for the Pre-Defueled Phase in the Decommissioning Transition Stage	2
Resolution Analysis of Fast Neutron Imaging Based on D-T Neutron Source	2
Exploring the Feasibility of Kuiper Belt Missions Supported by Centrifugal Nuclear Thermal Propulsion	2
Exploring Public Discourse About Spent Nuclear Fuel Management on Twitter	2
High-Fidelity Velocity and Concentration Measurements of Turbulent Buoyant Jets	2
UaSA Application in Severe Accident Analysis: Challenges and Path Forward	2
Direct Numerical Simulation of Single- and Two-Phase Flows for Nuclear Engineering Geometries	2
The Hypatia Experiment: Yttrium Hydride and Highly Enriched Uranium Critical Experiment	2
Trinity by the Numbers: The Computing Effort that Made Trinity Possible	2
Performance Evaluation of Batchwise Multistage Countercurrent Extraction in a LiCl–KCl/Cd System to Separate Actinides from Rare Earth Fission Products	2
Fiberoptic Laser-Induced Breakdown Spectroscopy System for in situ Measurement in a Hazardous Environment	2
Multiphysics Analysis of PLOFC and DLOFC Accidents in the HTGR-TR	2
Advanced Instrumentation and Modeling Framework for Two-Phase Flow	2
Influence of Iodine Chemistry in I 2 Scrubbing Modeling	2
Combustion Properties of Glove-Box Panel Resins Under Fire Accidents	2
A Fan-Controlled Sodium-to-Air Heat Exchanger Configuration for Failsafe Decay Heat Removal in Sodium-Cooled Fast Reactors	2
Novel Approach for Network Data Exchange Among Safety-Related Control Systems of Nuclear Reactors	2
A Pressure Drop and Particle Image Velocimetry Investigation into Depressurized Loss-of-Coolant Accident Parameters Applied to Packed Beds with an Aspect Ratio of D/d	2
Development of an Extended State Observer for Monitoring of a PWR Based on a Two-Point Kinetic Model	2
Detecting Anomalies in Simulated Nuclear Data Using Autoencoders	2
A MOOSE-Based Model for Fission Product Transport and Source Term Estimation for High-Temperature Gas-Cooled Reactors	2
Effect of Soil Properties and Input Motion on Site Amplification Using Validated Nonlinear Soil Model	2
Inferential-Statistical Reevaluation of Spent Fuel Zircaloy Cladding Integrity	2
Design and Application of an Airborne Radioactivity Survey System Based on Unmanned Aerial Vehicle	2
Prediction of Dispersed-Phase Holdup in Pulsed Disk and Doughnut Extraction Columns Using Machine Learning Methods	2
Refueling Considerations for 99 Mo Production in a CANDU Reactor	2
Adaptive Sampling Limit Surface Search Application to Identify Cliff-Edge Effects in Severe Accident Uncertainty Analysis	2
The Taming of Plutonium: Plutonium Metallurgy and the Manhattan Project	2
Automatic Generation of Event Trees and Fault Trees: A Model-Based Approach	2
Experimental Model to Study Characteristics of Radon Cover in Waste Landfills	2
Electron Target Cooling Analyses of the KIPT ADS Using MCNP and Ansys Fluent	2
Human Factors Considerations in Artificial Intelligence Applications for Nuclear Power Plants	2
Optimized FSF Controller for Bulk Power Control of Large-Core PHWRs	2
Research Activities Associated with the Treatment of Potential Common-Cause Failures in Event and Condition Assessments	2
TRACE Assessment for Simulating Density Wave Oscillations in a Full-Scale BWR Rod Bundle Under Natural Circulation	2
Versatile Testing Facility for Heavy Liquid Metal–Cooled Fast Reactor at the University of Pittsburgh	2
Detailed Analysis of the Effects of Spacer Grid and Mixing Vanes on Turbulence in a PWR Subchannel Under DFFB Conditions Based on DNS Data	2
Improvement of Radiological Waste Characterization with Bayesian Machine Learning	2
Role of Accelerated Burnup Irradiation Testing in Support of Accelerated Fuel Qualification	2
SAM: A Modern System Code for Advanced Non-LWR Safety Analysis	2
Explainable, Deep Reinforcement Learning–Based Decision Making for Operations and Maintenance	2
Analytical Model of Natural Circulation with a Sinusoidal Heat Input in a PWR	2
Safety-Related Instrumentation and Control Pilot Upgrade: Initial Scoping Phase Implementation and Lessons Learned	2
High-Fidelity Modeling and Experiments to Inform Safety Analysis Codes for Heat Pipe Microreactors	2
Numerical Analysis of Effects of Vane Deflection Angle on Flow-Thermal Characteristics in a Fuel Rod Assembly	2
Preventing Reverse Engineering of Critical Industrial Data with DIOD	2
Probabilistic Fracture Analysis for a Boiling Water Reactor Pressure Vessel During Transition to Decommissioning	2
Localization of Stationary and Moving Radiation Sources Using a Feedforward Neural Network with an Array of Sensors	2
Thermal-Hydraulic Characterization and Numerical Modeling with RELAP5 Code of ATHENA Secondary Loop	1
The Los Alamos Computing Facility During the Manhattan Project	1
Developments in Online Monitoring Technologies for Autonomous Microreactor Operations	1
Verification and Validation of Spectral Element Code for Supercritical CO2 Flow in Vertical Heated Tubes	1
Validation of Light Water Reactor Ex-Core Calculations with VERA	1
Evaluating Methods of Software Bill of Materials Generation to Enhance Nuclear Power Plant Cybersecurity	1
Introduction of Fusion Reactors as Transmutation Systems for Minor Actinides and Fission Products	1
Microstructural and Mechanical Properties of Nitrogen Ion Irradiated 316 Stainless Steel	1
Steady-State Irradiation of Characterized Instruments for Nuclear Thermal Rockets Using In-Pile Experiment Apparatus	1
Thermal Fluid Modeling Approaches in SAM for High Temperature Gas-Cooled Reactor Applications	1
Armoring Lightweight Foldable Radiator Panel for Lunar Surface Fission Power Systems	1
A Framework to Assess Advanced Reactor Spent Fuel Management Facility Deployment	1