OOIR: Observatory of International Research

Papers

(The median citation count of Nuclear Technology is 1. The table below lists those papers that are above that threshold based on CrossRef citation counts [max. 250 papers]. The publications cover those that have been published in the past four years, i.e., from 2021-06-01 to 2025-06-01.)

Article	Citations
Validation of Pronghorn Pressure Drop Correlations Against Pebble Bed Experiments	52
Thermal-Hydraulic Core Design of a Thorium-Based Molten Salt Fast Energy Amplifier	46
Nuclear Power Concepts and Development Strategies for High-Power Electric Propulsion Missions to Mars	25
Availability of Critical Benchmark Experiments for the Pebble Tanker Transportation Model for Nuclear Criticality Safety Validation of TRISO Pebbles	20
Comprehensive Study on p-n Junction and Schottky Barrier Betavoltaic Battery with ¹⁴ C Beta-Emitting Source	19
An Anisotropic Neutron Collimating System for Proton Accelerator-Generated Secondary Particles	19
Code Validation of SAM Using Forced and Natural Circulation Data from NACIE-UP Benchmark	18
Neutronics and Thermo-Fluids Simulation of Generic Pebble-Bed Fluoride-Salt-Cooled High-Temperature Reactor	18
Spatiotemporal Evaluation of Bubble Characteristics in Sodium Using Real-Time X-Ray Imaging	17
Verification and Demonstration of One-Dimensional Freezing Model in SAM for Salt-Cooled Reactor Analysis Applications	17
Best Estimate Plus Uncertainty Analysis of Station Blackout Transient in Pool-Type Research Reactor	17
Recent ²³⁸Pu Production Activities at Idaho National Laboratory	14
STORAGE: A Source Term Model for Intermediate-Level Radioactive Waste	14
Risk Plus Some Attributes (R + SA): A New Risk-Informed Method for Prioritizing Inspection Activities During New Fuel Facility Construction	14
Model Development for Thermal-Hydrology Simulations of a Full-Scale Heater Experiment in Opalinus Clay	14
Adsorption Properties of Cs(I) and Co(II) on GMZ Bentonite Colloids	13
Liquid Film Thickness for Gas-Liquid Annular Flow Across Grid Spacer with Vanes in Simple 3 × 3 Rod Bundle Channel	13
Examination of Deep Learning Algorithm for Nuclear Proliferation Risk Modeling	12
Enhancement of Fast Neutron Detection in Liquid Scintillator Detectors	12
Detection of Isotopes in Urban Source Search Low-Count Gamma Spectra Using Hopfield Neural Networks	12
Monte Carlo Analysis of Coolant Stream Impurity Gamma Emissions in Gas-Cooled Fast Reactors	11
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	11
Organic Telluride Formation from Paint Solvents Under Gamma Irradiation	10
Revisiting Mobile Paste Reactor Fuel	10
A Framework for Event Detection in Nuclear Facilities Using Wireless Sensors and Actors Networks	10

Development of a Signal Processing Software for Scintillation Detectors and Implementation on an FPGA for Fast Sensing	10
Comparison of Two Methods for Obtaining the Variabilities in a FRAM Model of a Combined Nuclear Facility Project	10
Effect of Nb Addition on Corrosion Resistance of U-6Zr Alloys	9
Research on Active Disturbance Rejection Control of Small Modular Reactor Once-Through Steam Generator Based on Differential Evolution Optimization Algorithm	9
Network Graph Laplacian-Based Sensor Projection in System-Level Modeling of Liquid-Metal Loop	9
Fluid Dynamics Effects of a Porous Blockage on Laminar Flow in the Interior Subchannels of a 61-Pin Wire-Wrapped Rod Bundle	9
Highly Available Nuclear Power in a Microgrid Configuration for the ORNL Distribution System	9
Comparative Study of Raman and EPMA Elemental Mapping of an Unirradiated MOX Sample	9
Comprehensive Study on Gamma-Ray, Neutron, and Charged Particle Shielding Properties of Glass Materials Using Analytical Methods and Monte Carlo Simulations	9
Thermal-Hydraulic Analysis of Inward and Outward Fuel Plate Buckling in a Typical MTR Reactor	8
The Use of High-Density UN Fuel in Heat-Pipe Microreactors	8
Pressure Drop Correlation Improvement for the Near-Wall Region of Pebble-Bed Reactors	8
Development of Two-Step Method for Fast Chloride MSR Neutronics	8
Assessing the Structure-Based Turbulence Model Performance for Thermal Striping Applications Using Symmetric Jet Experiments	8
A Structural Design Approach Tailored for the Rapid Preliminary Design of Microreactor Components	8
Adaptive Model Predictive Control for Heat Pipe–Cooled Microreactors Under Normal and Heat Pipe Failure Conditions	8
Nuclear Reactor Operations Education and Training with Virtual Reality and an Immersive Desktop Application	8
A RELAP5-3D Model of the Lobo Lead Loop	8
CHF Enhancement by γ-Fe ₂ O ₃ Nanofluids with Pool Boiling Condition on a Downward-Facing Plane	8
Development of Emergency Information System to Support Nuclear Power Plant Management in Severe Accident	7
Density Equation for Mixed Organic Solutions Containing tri- n -butyl Nitrate, n -Dodecane, Nitric Acid, and Nitrates of Heavy Metals	7
Validation Matrix for Pool Scrubbing Models	7
Determination of Gain Scheduling Parameters for Loss of a Feedwater Pump Transient Mitigation Using Neural Networks	7
Safety Benefits Assessment for Accident Tolerant Fuels in Consideration of Steam Generator Tube Degradation Using Dynamic Event Tree Analysis	7
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
Multiphase Turbulence Modeling Using Sparse Regression and Gene Expression Programming	6
The Versatile Loop Facility: A New Infrastructure for Testing Components and Systems of Lead Fast Reactor Technology	6
Sparse-View Neutron Computed Tomography 3-D Reconstruction via the Fast Gradient Projection Algorithm	6
Validation of a Countercurrent Gas Flow Model for Use in the Kairos Power System Analysis Module (KP-SAM) Code	6
Validation of a Hybrid Domain Overlapping Coupling Between SAM and CFD Against the TALL-3D Transients	6
Sensitivity Analysis of Transient Critical Heat Flux by RIA Under High-Pressure Flow Boiling Conditions in TRTL	6
Heat Transfer Analysis of Core Melt Contact with a CANDU Calandria	6
Direct Numerical Simulation and Large Eddy Simulation of a 67-Pebble-Bed Experiment	6
Prospects for Nuclear Microreactors: A Review of the Technology, Economics, and Regulatory Considerations	5
Systematic Component Investigation of the Steady-State High-Temperature In-Pile Nuclear Thermal Propulsion Experimental Test Bed	5
Mobile Application Development Plan for Fire Influence Analysis Using Algebraic Models	5
Research on the Preliminary Prediction of Nuclear Core Design Based on Machine Learning	5
Constructing Neural Network Model to Evaluate and Predict Human Error Probability in Nuclear Power Plants Based on Eye Response, Workload Rating, and Situation Awareness	5
Development of Subchannel Void Sensor for Wide Pressure and Temperature Ranges and Its Application to Boiling Flow Dynamics in a Heated Rod Bundle	5
Modal Decomposition of the Flow in a Randomly Packed Pebble Bed with Direct Numerical Simulation	5
Assessment of Screen-Covered Grooved Sodium Heat Pipes for Microreactor Applications	5
Acoustic Analysis of the Effects of Vapor-Liquid Interfacial Morphology on Pool-Boiling Heat Transfer	5
Validation and Neutronic Analysis of the CENM TRIGA MARK II SCALE Research Reactor Model: Computations Versus Experiment	5
Prognostics and Health Management for Maintenance-Dependent Processes	5
2D(r,θ) Simulations of the HBC-4 Power-to-Melt Experiment with the Fuel Performance Code ALCYONE	5
Path Toward a Breeding, Proliferation-Resistant, Thermal-Spectrum Molten Salt Reactor	5
Discrete Element Method Simulation of the Idaho Calcine Simulant for Hot Isostatic Pressing Canister Filling Process: Part 2	5
Finely Divided Metal as Nuclear Reactor Fuel	5

A Multiwire Proportional Chamber for Standardization of Large-Area Sources: Methodology and Challenges for In-House Construction	5
Radionuclide Transport in Channel Networks with Radial Diffusion in the Porous Rock Matrix	5
Nuclear Thermal-Hydraulic Phenomena: Bases and Challenges	5
Foreword: Special issue on the Nuclear Energy Advanced Modeling and Simulation Thermal Hydraulics Integrated Research Project	5
Enhancing Site Evaluation Standards for Nuclear Power Plants in Indonesia: Human-Induced External Events	5
Diagnostic Technique Characterizing Neutron Irradiation Effects on Additively Manufactured Inconel 625 Eliminating the Need for Remote Handling	5
The Experimental and Simulation Results of LIVE-J2 Test—Investigation on Heat Transfer in a Solid–Liquid Mixture Pool	4
Comparison of Irradiated TRISO Fuel Radioactivity from Multiple Advanced Reactor Designs	4
Neutron Energy Spectrum Measurement and Unfolding Method Based on a Single Long Lithium- or Boron-Doped Scintillator	4
The UO ₂ Power-to-Melt Experiment Performed in the High Burnup Chemistry International Program	4
Clogging Properties of HEPA Filter Induced by Loading of Soot from Burned Glove-Box Panel Materials	4
Indirect Parameterized Risk Assessment Applied to Brazilian Nuclear Sector	4
Remark About “Finely Divided Metal as Nuclear Reactor Fuel”	4
Optimizing the Implementation of Small Modular Reactors into Ontario’s Future Energy Mix	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
Time-Dependent Experiment on Reactor Power Distribution Estimation by Ex-Core Detectors at UTR-KINKI	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
On the Development of a Novel Acoustic Flowmeter for High-Temperature Gas-Cooled Reactors	4
Advanced Autonomous Welding for Refabrication and Follow-On Testing of Previously Irradiated Nuclear Fuel	4
Investigating the Heat Transfer Characteristics of Impinging Flow on a Downward-Facing Surface	4
Numerical Simulation on Dispersion of Hydrogen Leaked in Particle Layers of Glass Beads and Soil	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
Monte Carlo Perturbation Analysis of Fuel Temperature Variations in the MCNP Model of the Annular Core Research Reactor	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
Modeling of Lateral Flow in CFD for Subchannel Analysis	3
Technical Reviewers	3
Exploring the Feasibility of Quantum-Based Secure Communications for Nuclear Applications	3
Parametric Analysis of Radiological Impact from Hypothetical Accident Scenario at the Sanmen Nuclear Power Plant	3
On the Symmetry of Blast Waves	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
Uncertainty-Aware and Explainable Human Error Detection in the Operation of Nuclear Power Plants	3
Integrating Econometrics and Artificial Intelligence to Assess the Impact of Trade on Nuclear Proliferation	3
Preliminary Modeling of Chloride Deposition on Spent Nuclear Fuel Canisters in Dry Storage Relevant to Stress Corrosion Cracking	3
Availability of the Emergency Safety Electrical System of a Konvoi Nuclear Power Plant Considering Mobile Arrangements of Diesel Generators After Fukushima	3
Canadian Contributions to the Manhattan Project and Early Nuclear Research	3
Study on Flow Characteristics of Integrated Natural Circulation Reactor Under Inclined Conditions	3
Neutronic Analysis of the Conceptual Molten Uranium Breeder Reactor Using MCNP and SCALE Tools	3
Correction	3
In Situ Chlorine Generation and Rare Earth Chlorination by Molten Salt Electrolysis	3
Extrapolation of Monte Carlo–Derived Noble Gas Air-Submersion Effective Dose Rate Coefficients for Selected Occupational Settings to Other Geometries and Radionuclides	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
Denoising Algorithm for Subtle Anomaly Detection	3
Commentary	3
Safety Assessment Methodology for Transportation of Radioactive Material via Train	3
A Study on Boiling Heat Transfer Performance of TiO ₂ -CNTs Hybrid Nanofluid on a Downward-Facing Heating Surface	3
Calculation of Isotope-Specific Fission Rates for Neutrino Source Calculation in PWR Fuel Diversion Safeguarding	3
Lead Fast Reactor Thermal-Hydraulic Testing Facilities in Support of the UK Advanced Modular Reactor Program	3
Analysis of Influence of Tube Failure on Performance of Passive Residual Heat Removal Heat Exchanger	3
Global Divergence in Nuclear Power Plant Construction: The Role of Political Decentralization	3
SCALE 6.2.4 Validation for Light Water Reactor Decay Heat Analysis	3
Numerical Investigation of Changes in Heat Transfer Coefficient of Water-Aluminum Oxide Nanofluid Cooling in Nuclear Reactors	3
A Redundancy-Guided Approach for the Hazard Analysis of Digital Instrumentation and Control Systems in Advanced Nuclear Power Plants	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
Comparison of Neutron Radiation Response of Conventionally Wrought Versus Additive Manufacturing Production Methods in Alloy 625	3
Neutronics Calculation Advances at Los Alamos: Manhattan Project to Monte Carlo	3
Verification of Uncertainty Distributions for Thermal-Hydraulic Mixing Parameters Used in KWU-MIX for Pressurized Thermal Shock	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
Advancing Fixed-Source Reactor Analysis Through OpenNode Implementation	3
Application of Systems Usability Case in an Integrated System Validation of Control Room	3
Separating Nuclear Reactors from the Power Block with Heat Storage to Improve Economics with Dispatchable Heat and Electricity	3
Analysis of AP1000 Small-Break Loss-of-Coolant Accident Using Reactor Transient Simulator	3
Preventing Reverse Engineering of Critical Industrial Data with DIOD	3
Presentation of the xM3 Test Case of the P2M Simulation Exercise and Modeling with the Fuel Performance Code ALCYONE	3
Advanced Reactor Control and Operations (ARCO): A University Research Facility for Developing Optimized Digital Control Rooms	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
Multiphysics Analyses of the Bottom Components of the 3D Printed Transformational Challenge Reactor	3
First Experimental Demonstration of the Use of a Novel Planar Segmented HPGe Detector for Gamma Emission Tomography of Mockup Fuel Rods	3
Impact of Steel Equipment on Cyclotron Activation and Its Implications for Radioactive Waste Management	3
Evaluation of Reaction Rate Distribution Measurement in the Prototype Fast Reactor Monju	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
Preliminary Results for In-Situ Alternative Propellants for Nuclear Thermal Propulsion	2
Identification of Carbon in Glassy Cesium-Bearing Microparticles Using Electron Microscopy and Formation Mechanisms of the Microparticles	2
Stability Tests and Analysis of a Low-Pressure Natural Circulation Loop with Flashing Instability	2
Lumped Parameter Analysis of Autogenous Propellant Pressurization System for Nuclear Thermal Rocket	2
Adaptive Sampling Limit Surface Search Application to Identify Cliff-Edge Effects in Severe Accident Uncertainty Analysis	2
Comments on the Physics of the Frisch-Peierls Memorandum	2

A Fan-Controlled Sodium-to-Air Heat Exchanger Configuration for Failsafe Decay Heat Removal in Sodium-Cooled Fast Reactors	2
The Taming of Plutonium: Plutonium Metallurgy and the Manhattan Project	2
Enhanced Video-Level Anomaly Feature Detection for Nuclear Power Plant Component Inspections Using the Latency Mechanism	2
Optimized FSF Controller for Bulk Power Control of Large-Core PHWRs	2
Refueling Considerations for ⁹⁹ Mo Production in a CANDU Reactor	2
Automatic Generation of Event Trees and Fault Trees: A Model-Based Approach	2
Research Activities Associated with the Treatment of Potential Common-Cause Failures in Event and Condition Assessments	2
Trinity by the Numbers: The Computing Effort that Made Trinity Possible	2
A Batch Refueling Framework for Implementing the Sourdough Fuel Cycle and Waste Management Strategy in the EIRENE Novel Molten Salt Reactor Design	2
Influence of Iodine Chemistry in I ₂ Scrubbing Modeling	2
Optimization of Elliptical U-Tube Heat Exchanger (EUTHE) for Spray Cooling Based on the Taguchi and CFD Method	2
Opportunities, Challenges, and Research Needs for Remote Microreactor Operations	2
Novel Approach for Network Data Exchange Among Safety-Related Control Systems of Nuclear Reactors	2
High-Fidelity Velocity and Concentration Measurements of Turbulent Buoyant Jets	2
Calculated Critical and Subcritical Data for Revision of ANSI/ANS 8.12	2
Modeling of the P2M Past Fuel Melting Experiments with the Fuel Performance Code FAST-1.0.1	2
Hydrogen Generation from α Radiolysis of Organic Materials in Transuranic Waste. Comparison Between Experimental Data and STORAGE Calculations	2
Convolutional Neural Network–Aided Temperature Field Reconstruction: An Innovative Method for Advanced Reactor Monitoring	2
Analytical Model of Natural Circulation with a Sinusoidal Heat Input in a PWR	2
Resolution Analysis of Fast Neutron Imaging Based on D-T Neutron Source	2
Multiphysics Analysis of PLOFC and DLOFC Accidents in the HTGR-TR	2
Exploring Public Discourse About Spent Nuclear Fuel Management on Twitter	2
Prediction of Dispersed-Phase Holdup in Pulsed Disk and Doughnut Extraction Columns Using Machine Learning Methods	2
i-LAMP: Global, Industrywide Learning Aging Management Program for Neutron-Absorber Materials in Spent Fuel Pools	2
A Risk Approach to the Management for the Pre-Defueled Phase in the Decommissioning Transition Stage	2
Startup and Multiphysics Analysis of a Compact kW-Class Thermal Spectrum Microreactor	2
Versatile Testing Facility for Heavy Liquid Metal–Cooled Fast Reactor at the University of Pittsburgh	2
Advanced Instrumentation and Modeling Framework for Two-Phase Flow	2
Development of a Potential Facility Risk Index for Nuclear Safety and Security Using a Terrorism Scenario with a Hypothetical Nuclear Facility	2
Electron Target Cooling Analyses of the KIPT ADS Using MCNP and Ansys Fluent	2
Direct Numerical Simulation of Single- and Two-Phase Flows for Nuclear Engineering Geometries	2
Fiberoptic Laser-Induced Breakdown Spectroscopy System for in situ Measurement in a Hazardous Environment	2
Hydride Transformations and Their Impact on Zirconium Alloy Cladding Embrittlement During Spent Nuclear Fuel Storage	2
Experimental Method for Verification of Calculated ¹³⁷Cs Content in Nuclear Fuel Assemblies	2
The Hypatia Experiment: Yttrium Hydride and Highly Enriched Uranium Critical Experiment	2
High-Fidelity Modeling and Experiments to Inform Safety Analysis Codes for Heat Pipe Microreactors	2
Inferential-Statistical Reevaluation of Spent Fuel Zircaloy Cladding Integrity	2
Experimental Model to Study Characteristics of Radon Cover in Waste Landfills	2
Simulation and Mitigation of False Data Injection Cyberattacks on a Space Nuclear Reactor Power System	2
Development of an Extended State Observer for Monitoring of a PWR Based on a Two-Point Kinetic Model	2
Exploring the Feasibility of Kuiper Belt Missions Supported by Centrifugal Nuclear Thermal Propulsion	2
Assessment of Factory Fabrication Considerations for Nuclear Microreactors	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
Correlation Method of 3-D Detection of Distant Sources of Gamma Radiation and Neutrinos by Intensity Interferometry	2
A MOOSE-Based Model for Fission Product Transport and Source Term Estimation for High-Temperature Gas-Cooled Reactors	2
Void Fraction and Interfacial Friction in Vertical Circular Pipes with the Square Top End Under Flooding Conditions	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
Safety-Related Instrumentation and Control Pilot Upgrade: Initial Scoping Phase Implementation and Lessons Learned	2
Qualification of Metallic Fuel Data for Advanced SFR Applications	2
Digitalization, Management, and Synthesis of Thermal-Hydraulic Legacy Data Using the Dynamical System Scaling	2
Numerical Simulations of Flow-Induced Deflections in MITR LEU Fuel Plate Due to Channel Size Disparity	2
Numerical Analysis of Effects of Vane Deflection Angle on Flow-Thermal Characteristics in a Fuel Rod Assembly	2
Release Behavior of Gaseous Ruthenium Tetroxide During Heating of High-Level Liquid Waste Simulant During Simulated Accident Conditions	2
Uncertainty Quantification for Multiphase Computational Fluid Dynamics Closure Relations with a Physics-Informed Bayesian Approach	2
Explainable, Deep Reinforcement Learning–Based Decision Making for Operations and Maintenance	2
Electrochemical Identification of Metal Chlorides in Eutectic LiCl-KCl Without Prior Knowledge of Analyte Identities	2
SAM: A Modern System Code for Advanced Non-LWR Safety Analysis	2
Bayesian Network–Based Fault Diagnostic System for Nuclear Power Plant Assets	2
Constitutive Modeling of Anisotropic Plasticity with ML Algorithms in Metals	2
Human Factors Considerations in Artificial Intelligence Applications for Nuclear Power Plants	2
Simplified Reactor Model for Microreactor Coupled with Helium Closed Brayton Cycle	2
Improvement of Radiological Waste Characterization with Bayesian Machine Learning	2
TRACE Assessment for Simulating Density Wave Oscillations in a Full-Scale BWR Rod Bundle Under Natural Circulation	2
Detecting Anomalies in Simulated Nuclear Data Using Autoencoders	2
Thermal Assessment of Repository Footprint Requirement for Advanced Fuel Cycles	2
Performance Evaluation of Batchwise Multistage Countercurrent Extraction in a LiCl–KCl/Cd System to Separate Actinides from Rare Earth Fission Products	2
Design of Moderator Assemblies for Fast, Epithermal, or Thermal Neutron–Dominated n-γ Mixed Fields Using a D-D Neutron Source	2
Computational Framework for Estimating Cost of Equipment Disposal for Advanced Reactors	2
Irregular, Backward-Compatible PWR Assembles with More Pins to Facilitate Uprates	2
Benchmarking Neutron Counting System for Passive Measurements and Active Interrogation of Unknown Objects for Fissile and Fissionable Materials Determination	2
Investigation of High-Temperature Compatibility of Select Oxides with Yttrium Hydride for Micro and Space Reactor Applications	2
Combustion Properties of Glove-Box Panel Resins Under Fire Accidents	2
Effect of Soil Properties and Input Motion on Site Amplification Using Validated Nonlinear Soil Model	2
Evaluation of Fukushima Daiichi Unit 1 Ex-Vessel Phenomenon Leveraging on Primary Containment Vessel Robotic Inspections	1
Tailoring ZrWNb-Based Refractory High Entropy Alloys: A Multidirectional Characterization Through Elemental, Physical, Thermodynamic, and Nuclear Radiation Attenuation Properties	1
Drying and Analysis of Aluminum (Oxy)hydroxide Films for Dry Storage of Aluminum-Clad Spent Nuclear Fuels	1
A Cable Condition Monitoring Strategy for Safe and Reliable Plant Operation	1
Modeling of the P2M Past Fuel Melting Experiments with the FEMAXI-8 Code	1
Validation of Light Water Reactor Ex-Core Calculations with VERA	1
Thermal-Hydraulic Characterization and Numerical Modeling with RELAP5 Code of ATHENA Secondary Loop	1
Introduction of Fusion Reactors as Transmutation Systems for Minor Actinides and Fission Products	1
PCMI Uncertainty and Sensitivity Analysis of Es-Salam Reactor Fuel Rods During Steady-State Operations	1
Technical Reviewers	1
Multiphase Species Transport Modeling for Molten Salt Reactors in the System Analysis Module: Generation, Decay, Deposition, and Extraction of Insoluble Fission Products	1
A Framework to Assess Advanced Reactor Spent Fuel Management Facility Deployment	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
Geopolymers as Emerging Materials for Immobilization of Toxic Radionuclides	1
Safeguards and Security for High-Burnup TRISO Pebble Bed Spent Fuel and Reactors	1
Condition Assessment of Nuclear Power Plant Equipment Based on Machine Learning Methods: A Review	1
Foreword: Selected papers from the 12th Japan-U.S. Seminar on Two-Phase Flow Dynamics	1
Microstructural and Mechanical Properties of Nitrogen Ion Irradiated 316 Stainless Steel	1
Developments in Online Monitoring Technologies for Autonomous Microreactor Operations	1
Evaluating Methods of Software Bill of Materials Generation to Enhance Nuclear Power Plant Cybersecurity	1
The Los Alamos Computing Facility During the Manhattan Project	1