Nuclear Technology

Article	Citations
Best Estimate Plus Uncertainty Analysis of Station Blackout Transient in Pool-Type Research Reactor	49
Model Development for Thermal-Hydrology Simulations of a Full-Scale Heater Experiment in Opalinus Clay	42
Spatiotemporal Evaluation of Bubble Characteristics in Sodium Using Real-Time X-Ray Imaging	24
Validation of Pronghorn Pressure Drop Correlations Against Pebble Bed Experiments	19
Hybrid System Level and Coarse Grid CFD Tool for Three-Dimensional Natural Circulation, Mixing, and Stratification Modeling	19
Thermal-Hydraulic Core Design of a Thorium-Based Molten Salt Fast Energy Amplifier	19
Nuclear Power Concepts and Development Strategies for High-Power Electric Propulsion Missions to Mars	18
Verification and Demonstration of One-Dimensional Freezing Model in SAM for Salt-Cooled Reactor Analysis Applications	17
Recent 238Pu Production Activities at Idaho National Laboratory	16
Risk Plus Some Attributes (R + SA): A New Risk-Informed Method for Prioritizing Inspection Activities During New Fuel Facility Construction	16
Availability of Critical Benchmark Experiments for the Pebble Tanker Transportation Model for Nuclear Criticality Safety Validation of TRISO Pebbles	14
Code Validation of SAM Using Forced and Natural Circulation Data from NACIE-UP Benchmark	13
Monte Carlo Analysis of Coolant Stream Impurity Gamma Emissions in Gas-Cooled Fast Reactors	13
Neutronics and Thermo-Fluids Simulation of Generic Pebble-Bed Fluoride-Salt-Cooled High-Temperature Reactor	13
STORAGE: A Source Term Model for Intermediate-Level Radioactive Waste	13
Liquid Film Thickness for Gas-Liquid Annular Flow Across Grid Spacer with Vanes in Simple 3 × 3 Rod Bundle Channel	12
Revisiting Mobile Paste Reactor Fuel	12
Development of a Signal Processing Software for Scintillation Detectors and Implementation on an FPGA for Fast Sensing	12
Comparison of Two Methods for Obtaining the Variabilities in a FRAM Model of a Combined Nuclear Facility Project	11
Comparative Study of Raman and EPMA Elemental Mapping of an Unirradiated MOX Sample	10
Adsorption Properties of Cs(I) and Co(II) on GMZ Bentonite Colloids	10
Effect of Nb Addition on Corrosion Resistance of U-6Zr Alloys	10
Research on Active Disturbance Rejection Control of Small Modular Reactor Once-Through Steam Generator Based on Differential Evolution Optimization Algorithm	10
A Framework for Event Detection in Nuclear Facilities Using Wireless Sensors and Actors Networks	10
Organic Telluride Formation from Paint Solvents Under Gamma Irradiation	10

Detection of Isotopes in Urban Source Search Low-Count Gamma Spectra Using Hopfield Neural Networks	10
Highly Available Nuclear Power in a Microgrid Configuration for the ORNL Distribution System	10
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
Examination of Deep Learning Algorithm for Nuclear Proliferation Risk Modeling	9
Enhancement of Fast Neutron Detection in Liquid Scintillator Detectors	9
In-Canal Assay of High Specific Activity 60Co at the Advanced Test Reactor	9
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	9
Nuclear Reactor Operations Education and Training with Virtual Reality and an Immersive Desktop Application	8
Adaptive Model Predictive Control for Heat Pipe–Cooled Microreactors Under Normal and Heat Pipe Failure Conditions	8
Safety Benefits Assessment for Accident Tolerant Fuels in Consideration of Steam Generator Tube Degradation Using Dynamic Event Tree Analysis	8
The Use of High-Density UN Fuel in Heat-Pipe Microreactors	8
Assessing the Structure-Based Turbulence Model Performance for Thermal Striping Applications Using Symmetric Jet Experiments	8
A RELAP5-3D Model of the Lobo Lead Loop	8
The Versatile Loop Facility: A New Infrastructure for Testing Components and Systems of Lead Fast Reactor Technology	8
Thermal-Hydraulic Analysis of Inward and Outward Fuel Plate Buckling in a Typical MTR Reactor	8
CHF Enhancement by γ-Fe 2 O 3 Nanofluids with Pool Boiling Condition on a Downward-Facing Plane	7
Validation Matrix for Pool Scrubbing Models	7
Evaluating Material Attractiveness of Minor Actinide Nuclear Fuel Intended for a Waste Transmutation Lead-Cooled Fast Reactor	7
A Structural Design Approach Tailored for the Rapid Preliminary Design of Microreactor Components	7
Development of Two-Step Method for Fast Chloride MSR Neutronics	7
Development of Emergency Information System to Support Nuclear Power Plant Management in Severe Accident	7
Determination of Gain Scheduling Parameters for Loss of a Feedwater Pump Transient Mitigation Using Neural Networks	6
Prognostics and Health Management for Maintenance-Dependent Processes	6
Effect of Nozzle Diameter on Quenching Behavior of Simulant Material CaO-Fe2O3 Under Bottom Flooding Conditions	6
Pressure Drop Correlation Improvement for the Near-Wall Region of Pebble-Bed Reactors	6
Density Equation for Mixed Organic Solutions Containing tri- n -butyl Nitrate, n -Dodecane, Nitric Acid, and Nitrates of Heavy Metals	6
Multiphase Turbulence Modeling Using Sparse Regression and Gene Expression Programming	6
Systematic Component Investigation of the Steady-State High-Temperature In-Pile Nuclear Thermal Propulsion Experimental Test Bed	6
Sensitivity Analysis of Transient Critical Heat Flux by RIA Under High-Pressure Flow Boiling Conditions in TRTL	6
Validation of a Countercurrent Gas Flow Model for Use in the Kairos Power System Analysis Module (KP-SAM) Code	5
Remark About “Finely Divided Metal as Nuclear Reactor Fuel”	5
Time-Dependent Experiment on Reactor Power Distribution Estimation by Ex-Core Detectors at UTR-KINKI	5
Diagnostic Technique Characterizing Neutron Irradiation Effects on Additively Manufactured Inconel 625 Eliminating the Need for Remote Handling	5
Assessment of Screen-Covered Grooved Sodium Heat Pipes for Microreactor Applications	5
Finely Divided Metal as Nuclear Reactor Fuel	5
Radionuclide Transport in Channel Networks with Radial Diffusion in the Porous Rock Matrix	5
A Multiwire Proportional Chamber for Standardization of Large-Area Sources: Methodology and Challenges for In-House Construction	5
Validation and Neutronic Analysis of the CENM TRIGA MARK II SCALE Research Reactor Model: Computations Versus Experiment	5
Research on the Preliminary Prediction of Nuclear Core Design Based on Machine Learning	5
Nuclear Thermal-Hydraulic Phenomena: Bases and Challenges	5
Acoustic Analysis of the Effects of Vapor-Liquid Interfacial Morphology on Pool-Boiling Heat Transfer	5
Validation of a Hybrid Domain Overlapping Coupling Between SAM and CFD Against the TALL-3D Transients	5
Heat Transfer Analysis of Core Melt Contact with a CANDU Calandria	5
Prospects for Nuclear Microreactors: A Review of the Technology, Economics, and Regulatory Considerations	5
Optimizing the Implementation of Small Modular Reactors into Ontario’s Future Energy Mix	5
Investigating the Heat Transfer Characteristics of Impinging Flow on a Downward-Facing Surface	5
Direct Numerical Simulation and Large Eddy Simulation of a 67-Pebble-Bed Experiment	5
Mobile Application Development Plan for Fire Influence Analysis Using Algebraic Models	5
Development and Verification of Neutron Kinetics Parameter Calculation Program Applicable to Subcritical Systems of Long-Life Reactors	5

Sparse-View Neutron Computed Tomography 3-D Reconstruction via the Fast Gradient Projection Algorithm	5
Development of Subchannel Void Sensor for Wide Pressure and Temperature Ranges and Its Application to Boiling Flow Dynamics in a Heated Rod Bundle	4
Verification of Uncertainty Distributions for Thermal-Hydraulic Mixing Parameters Used in KWU-MIX for Pressurized Thermal Shock	4
Enhancing Site Evaluation Standards for Nuclear Power Plants in Indonesia: Human-Induced External Events	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
Evaluation of Reaction Rate Distribution Measurement in the Prototype Fast Reactor Monju	4
Advanced Autonomous Welding for Refabrication and Follow-On Testing of Previously Irradiated Nuclear Fuel	4
The Experimental and Simulation Results of LIVE-J2 Test—Investigation on Heat Transfer in a Solid–Liquid Mixture Pool	4
Investigation of the Thermal Effects of MgO and ZnO Nanoparticles in a Pressurized Water Reactor Coolant with Computational Fluid Dynamics Model	4
Investigation of Buildup Region and Surface Dose: Comparison of Parallel Plane Ion Chamber, Treatment Planning System, and MC Simulation	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
Foreword: Special issue on the Nuclear Energy Advanced Modeling and Simulation Thermal Hydraulics Integrated Research Project	4
Discrete Element Method Simulation of the Idaho Calcine Simulant for Hot Isostatic Pressing Canister Filling Process: Part 2	4
Comparison of Irradiated TRISO Fuel Radioactivity from Multiple Advanced Reactor Designs	4
On the Development of a Novel Acoustic Flowmeter for High-Temperature Gas-Cooled Reactors	4
Numerical Simulation on Dispersion of Hydrogen Leaked in Particle Layers of Glass Beads and Soil	4
2D(r,θ) Simulations of the HBC-4 Power-to-Melt Experiment with the Fuel Performance Code ALCYONE	4
In Situ Chlorine Generation and Rare Earth Chlorination by Molten Salt Electrolysis	3
Modeling of the P2M Past Fuel Melting Experiments with the Fuel Performance Code FAST-1.0.1	3
Technical Reviewers	3
Analysis of AP1000 Small-Break Loss-of-Coolant Accident Using Reactor Transient Simulator	3
Numerical Investigation of Changes in Heat Transfer Coefficient of Water-Aluminum Oxide Nanofluid Cooling in Nuclear Reactors	3
Advancing Fixed-Source Reactor Analysis Through OpenNode Implementation	3
Uncertainty-Aware and Explainable Human Error Detection in the Operation of Nuclear Power Plants	3
Considerations for Hydride Moderator Readiness in Microreactors	3
Neutronics Calculation Advances at Los Alamos: Manhattan Project to Monte Carlo	3
On the Symmetry of Blast Waves	3
Neutronic Analysis of the Conceptual Molten Uranium Breeder Reactor Using MCNP and SCALE Tools	3
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	3
Modeling of Lateral Flow in CFD for Subchannel Analysis	3
The UO 2 Power-to-Melt Experiment Performed in the High Burnup Chemistry International Program	3
Multiphysics Analyses of the Bottom Components of the 3D Printed Transformational Challenge Reactor	3
Canadian Contributions to the Manhattan Project and Early Nuclear Research	3
Advanced Reactor Control and Operations (ARCO): A University Research Facility for Developing Optimized Digital Control Rooms	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
Separating Nuclear Reactors from the Power Block with Heat Storage to Improve Economics with Dispatchable Heat and Electricity	3
Analysis of Influence of Tube Failure on Performance of Passive Residual Heat Removal Heat Exchanger	3
SCALE 6.2.4 Validation for Light Water Reactor Decay Heat Analysis	3
Protected Loss-of-Flow Accident in a HLM Pool Facility: Long-Term Cooling Experiment	3
A Study on Boiling Heat Transfer Performance of TiO 2 -CNTs Hybrid Nanofluid on a Downward-Facing Heating Surface	3
First Experimental Demonstration of the Use of a Novel Planar Segmented HPGe Detector for Gamma Emission Tomography of Mockup Fuel Rods	3
Availability of the Emergency Safety Electrical System of a Konvoi Nuclear Power Plant Considering Mobile Arrangements of Diesel Generators After Fukushima	3
The Trinity High-Explosive Implosion System: The Foundation for Precision Explosive Applications	3
Comparison of Neutron Radiation Response of Conventionally Wrought Versus Additive Manufacturing Production Methods in Alloy 625	3
Comment on Comparison Between Historic Nuclear Explosion Yield Formulas	3
Lead Fast Reactor Thermal-Hydraulic Testing Facilities in Support of the UK Advanced Modular Reactor Program	3
Correlation Method of 3-D Detection of Distant Sources of Gamma Radiation and Neutrinos by Intensity Interferometry	3
Commentary	3
Presentation of the xM3 Test Case of the P2M Simulation Exercise and Modeling with the Fuel Performance Code ALCYONE	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
Application of FSVD Algorithm to Airborne Gamma Detection of Trace Radionuclides in the Process of a High Radon Background	3
Calculation of Isotope-Specific Fission Rates for Neutrino Source Calculation in PWR Fuel Diversion Safeguarding	3
Exploring the Feasibility of Quantum-Based Secure Communications for Nuclear Applications	3
Safety Assessment Methodology for Transportation of Radioactive Material via Train	3
Denoising Algorithm for Subtle Anomaly Detection	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
A Way of Analyzing an Oxide Layer on Irradiated Plate-Type Atomized U-Mo Fuel Using an EPMA and X-Ray Image Mapping	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
Monte Carlo Perturbation Analysis of Fuel Temperature Variations in the MCNP Model of the Annular Core Research Reactor	3
Clogging Properties of HEPA Filter Induced by Loading of Soot from Burned Glove-Box Panel Materials	3
Digitalization, Management, and Synthesis of Thermal-Hydraulic Legacy Data Using the Dynamical System Scaling	2
The Hypatia Experiment: Yttrium Hydride and Highly Enriched Uranium Critical Experiment	2
Exploring the Feasibility of Kuiper Belt Missions Supported by Centrifugal Nuclear Thermal Propulsion	2
Computational Framework for Estimating Cost of Equipment Disposal for Advanced Reactors	2
Direct Numerical Simulation of Single- and Two-Phase Flows for Nuclear Engineering Geometries	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
Multiscale Simulations of Thermal Transport in W-UO2 CERMET Fuel for Nuclear Thermal Propulsion	2
A Risk Approach to the Management for the Pre-Defueled Phase in the Decommissioning Transition Stage	2
Numerical Analysis of Effects of Vane Deflection Angle on Flow-Thermal Characteristics in a Fuel Rod Assembly	2
Identification of Carbon in Glassy Cesium-Bearing Microparticles Using Electron Microscopy and Formation Mechanisms of the Microparticles	2
SAM: A Modern System Code for Advanced Non-LWR Safety Analysis	2
Release Behavior of Gaseous Ruthenium Tetroxide During Heating of High-Level Liquid Waste Simulant During Simulated Accident Conditions	2
Electrochemical Identification of Metal Chlorides in Eutectic LiCl-KCl Without Prior Knowledge of Analyte Identities	2
Inferential-Statistical Reevaluation of Spent Fuel Zircaloy Cladding Integrity	2
Void Fraction and Interfacial Friction in Vertical Circular Pipes with the Square Top End Under Flooding Conditions	2
Experimental Method for Verification of Calculated 137Cs Content in Nuclear Fuel Assemblies	2
Lightweight Heat Pipe Radiator for Nuclear Reactor Power Systems on Lunar Surface	2
Multiphysics Analysis of PLOFC and DLOFC Accidents in the HTGR-TR	2
A Redundancy-Guided Approach for the Hazard Analysis of Digital Instrumentation and Control Systems in Advanced Nuclear Power Plants	2

Thermal Assessment of Repository Footprint Requirement for Advanced Fuel Cycles	2
Integral-Effect Test for Loss of Residual Heat Removal System During Mid-Loop Operation in ATLAS Facility	2
Lumped Parameter Analysis of Autogenous Propellant Pressurization System for Nuclear Thermal Rocket	2
Convolutional Neural Network–Aided Temperature Field Reconstruction: An Innovative Method for Advanced Reactor Monitoring	2
High-Fidelity Velocity and Concentration Measurements of Turbulent Buoyant Jets	2
Optimized FSF Controller for Bulk Power Control of Large-Core PHWRs	2
Investigation of High-Temperature Compatibility of Select Oxides with Yttrium Hydride for Micro and Space Reactor Applications	2
Optimization of Elliptical U-Tube Heat Exchanger (EUTHE) for Spray Cooling Based on the Taguchi and CFD Method	2
Development of a Potential Facility Risk Index for Nuclear Safety and Security Using a Terrorism Scenario with a Hypothetical Nuclear Facility	2
Irregular, Backward-Compatible PWR Assembles with More Pins to Facilitate Uprates	2
Trinity by the Numbers: The Computing Effort that Made Trinity Possible	2
Automatic Generation of Event Trees and Fault Trees: A Model-Based Approach	2
Comments on the Physics of the Frisch-Peierls Memorandum	2
Calculated Critical and Subcritical Data for Revision of ANSI/ANS 8.12	2
Versatile Testing Facility for Heavy Liquid Metal–Cooled Fast Reactor at the University of Pittsburgh	2
Experimental Model to Study Characteristics of Radon Cover in Waste Landfills	2
Influence of Iodine Chemistry in I 2 Scrubbing Modeling	2
Prediction of Dispersed-Phase Holdup in Pulsed Disk and Doughnut Extraction Columns Using Machine Learning Methods	2
Electron Target Cooling Analyses of the KIPT ADS Using MCNP and Ansys Fluent	2
Stability Tests and Analysis of a Low-Pressure Natural Circulation Loop with Flashing Instability	2
Numerical Simulations of Flow-Induced Deflections in MITR LEU Fuel Plate Due to Channel Size Disparity	2
Research Activities Associated with the Treatment of Potential Common-Cause Failures in Event and Condition Assessments	2
Impact of Steel Equipment on Cyclotron Activation and Its Implications for Radioactive Waste Management	2
Startup and Multiphysics Analysis of a Compact kW-Class Thermal Spectrum Microreactor	2
Study on Flow Characteristics of Integrated Natural Circulation Reactor Under Inclined Conditions	2
Development of an Extended State Observer for Monitoring of a PWR Based on a Two-Point Kinetic Model	2
Correction	2
Uncertainty Quantification for Multiphase Computational Fluid Dynamics Closure Relations with a Physics-Informed Bayesian Approach	2
TRACE Assessment for Simulating Density Wave Oscillations in a Full-Scale BWR Rod Bundle Under Natural Circulation	2
A Fan-Controlled Sodium-to-Air Heat Exchanger Configuration for Failsafe Decay Heat Removal in Sodium-Cooled Fast Reactors	2
Global Divergence in Nuclear Power Plant Construction: The Role of Political Decentralization	2
Bayesian Network–Based Fault Diagnostic System for Nuclear Power Plant Assets	2
Advanced Instrumentation and Modeling Framework for Two-Phase Flow	2
Adaptive Sampling Limit Surface Search Application to Identify Cliff-Edge Effects in Severe Accident Uncertainty Analysis	2
Fiberoptic Laser-Induced Breakdown Spectroscopy System for in situ Measurement in a Hazardous Environment	2
i-LAMP: Global, Industrywide Learning Aging Management Program for Neutron-Absorber Materials in Spent Fuel Pools	2
Performance Evaluation of Batchwise Multistage Countercurrent Extraction in a LiCl–KCl/Cd System to Separate Actinides from Rare Earth Fission Products	2
Resolution Analysis of Fast Neutron Imaging Based on D-T Neutron Source	2
Assessment of Factory Fabrication Considerations for Nuclear Microreactors	2
Exploring Public Discourse About Spent Nuclear Fuel Management on Twitter	2
Enhanced Video-Level Anomaly Feature Detection for Nuclear Power Plant Component Inspections Using the Latency Mechanism	2
Safety-Related Instrumentation and Control Pilot Upgrade: Initial Scoping Phase Implementation and Lessons Learned	2
Extrapolation of Monte Carlo–Derived Noble Gas Air-Submersion Effective Dose Rate Coefficients for Selected Occupational Settings to Other Geometries and Radionuclides	2
Detecting Anomalies in Simulated Nuclear Data Using Autoencoders	2
Application of Systems Usability Case in an Integrated System Validation of Control Room	2
Constitutive Modeling of Anisotropic Plasticity with ML Algorithms in Metals	2
Preventing Reverse Engineering of Critical Industrial Data with DIOD	2
Human Factors Considerations in Artificial Intelligence Applications for Nuclear Power Plants	2
Effect of Soil Properties and Input Motion on Site Amplification Using Validated Nonlinear Soil Model	2
Explainable, Deep Reinforcement Learning–Based Decision Making for Operations and Maintenance	2
Preliminary Modeling of Chloride Deposition on Spent Nuclear Fuel Canisters in Dry Storage Relevant to Stress Corrosion Cracking	2
The Taming of Plutonium: Plutonium Metallurgy and the Manhattan Project	2