Nuclear Technology

Article	Citations
Thermal-Hydraulic Core Design of a Thorium-Based Molten Salt Fast Energy Amplifier	83
STORAGE: A Source Term Model for Intermediate-Level Radioactive Waste	31
Validation of Pronghorn Pressure Drop Correlations Against Pebble Bed Experiments	30
An Anisotropic Neutron Collimating System for Proton Accelerator–Generated Secondary Particles	30
Model Development for Thermal-Hydrology Simulations of a Full-Scale Heater Experiment in Opalinus Clay	29
Spatiotemporal Evaluation of Bubble Characteristics in Sodium Using Real-Time X-Ray Imaging	29
Availability of Critical Benchmark Experiments for the Pebble Tanker Transportation Model for Nuclear Criticality Safety Validation of TRISO Pebbles	22
Simulation of a Slow Loss-of-Flow Accident in an Open-Pool Research Reactor Using Computational Fluid Dynamics	17
FAST Irradiations, Postirradiation Examinations, and Modeling of U-Mo for Light Water Reactor Applications	16
Code Validation of SAM Using Forced and Natural Circulation Data from NACIE-UP Benchmark	16
Risk Plus Some Attributes (R + SA): A New Risk-Informed Method for Prioritizing Inspection Activities During New Fuel Facility Construction	15
MARVEL Authorization Process	15
Study on Aerosol Deposition Characteristics of an Obstacle Structure During Ventilation for Fukushima Daiichi Decommissioning	14
Optimizing Transmission Expansion for Sustainable Energy Integration in Ghana: A Multiscenario Analysis of Nuclear and Renewable Synergies Within the West African Power Pool Framework	13
Assessment of RELAP5-3D Code with Molten Salt Heat Transfer Experiments	13
Interpreting Thermally and Hydrodynamically Controlled Regions in Subcooled Flow Boiling	12
Optimized Synthesis and Evaluation of Composite Beads for Antimony Removal from Acidic Nuclear Reprocessing Effluent	12
Long-Lived Fission Products Transmutation in Fission-Free Thermal Accelerator-Driven Transmuter	12
Best Estimate Plus Uncertainty Analysis of Station Blackout Transient in Pool-Type Research Reactor	12
Neutronics and Thermo-Fluids Simulation of Generic Pebble-Bed Fluoride-Salt-Cooled High-Temperature Reactor	12
The Design and Development of the Process Radiation Monitoring System of the High Temperature Gas-Cooled Reactor (HTGR) in China	11
Safety Classification of Modular HTGRs Based on the IAEA SSG-30 Method	11
Depletion Benchmark Analysis on a Lead Fast Reactor Using PyARC/OpenMC	10
Uncertainty Assessment of an iSMR Passive Safety System: Model Lifecycle Management Study Case	10
Verification and Demonstration of One-Dimensional Freezing Model in SAM for Salt-Cooled Reactor Analysis Applications	10

Molten Salt Contaminant Detection Part I: Feature Selection on Cyclic-Voltammetry Data for Digital Asset Management	9
Machine Learning Methods for Predicting Mean and Uncertainty in Nodal Cross-Section Libraries	9
Recent 238 Pu Production Activities at Idaho National Laboratory	9
Developing a Monte Carlo–Based Fault Tree Quantification Module for SAPHIRE Targeting Seismic Probabilistic Risk Assessments	9
Mapping the Hydrogen Economy in Ghana: The Strategic Contribution of Small Modular Reactors	8
Revisiting Mobile Paste Reactor Fuel	8
Examination of Deep Learning Algorithm for Nuclear Proliferation Risk Modeling	8
Comprehensive Study on p-n Junction and Schottky Barrier Betavoltaic Battery with 14 C Beta-Emitting Source	8
Liquid Film Thickness for Gas-Liquid Annular Flow Across Grid Spacer with Vanes in Simple 3 × 3 Rod Bundle Channel	8
Methods for Extending the Reactor Core Lifetime of the Canadian Thermal Battery TM	8
Monte Carlo Analysis of Coolant Stream Impurity Gamma Emissions in Gas-Cooled Fast Reactors	8
Network Graph Laplacian-Based Sensor Projection in System-Level Modeling of Liquid-Metal Loop	8
Fluid Dynamics Effects of a Porous Blockage on Laminar Flow in the Interior Subchannels of a 61-Pin Wire-Wrapped Rod Bundle	8
Research on Active Disturbance Rejection Control of Small Modular Reactor Once-Through Steam Generator Based on Differential Evolution Optimization Algorithm	7
Effect of Nb Addition on Corrosion Resistance of U-6Zr Alloys	7
Comparative Study of Raman and EPMA Elemental Mapping of an Unirradiated MOX Sample	7
Implementation and Demonstration of the Digital Twin Certification System Remote Operations Framework	7
Data-Informed Evaluation Framework for Integrated Energy Systems: Insights from Power, Process Heat, and Hydrogen Production Applications	7
Development of a Signal Processing Software for Scintillation Detectors and Implementation on an FPGA for Fast Sensing	7
“Arturo” Nuclear Power Plant and the Technopolitics of Italian Nuclear Decommissioning	7
Comparison of Two Methods for Obtaining the Variabilities in a FRAM Model of a Combined Nuclear Facility Project	7
The Origins of Nuclear Expertise: The Formation of Nuclear Engineering Education in the US and Sweden (1950–1979)	7
Sociotechnical Readiness Level and Natural Language Processing: Tools for Measuring and Managing Societal Acceptance of Nuclear Energy	7
Gamma-Ray Shielding Performance of Ho 2 O 3 –Doped Borate Glasses: Influence of ZnO and CaO Substi	6
Thermal-Hydraulic Analysis of Inward and Outward Fuel Plate Buckling in a Typical MTR Reactor	6
CHF Enhancement by γ-Fe 2 O 3 Nanofluids with Pool Boiling Condition on a Downward-Facing Plane	6
An Uncertainty Quantification Method for Neutronics Parameters in the Pressurized Water Reactor Core Control System	6
The Effect of MgO, CaO, and SrO on the Optical Properties and Radiation Attenuation Behavior of Sb 2 O 3	6
Detection of Isotopes in Urban Source Search Low-Count Gamma Spectra Using Hopfield Neural Networks	6
Boiling and Drying Accident of High-Level Liquid Waste in a Reprocessing Plant: Measurement of the Liquid-Phase Mass Transfer Coefficients of NO 2 an	6
FNERCs Software for Fast Neutron Shielding Assessment Based on ENDF/B-VIII.0, ENDF/B-VIII.1, and TENDL Libraries	6
A Structural Design Approach Tailored for the Rapid Preliminary Design of Microreactor Components	6
Explaining System-Level Prognostics with Established Machine Learning Methods	6
Comprehensive Study on Gamma-Ray, Neutron, and Charged Particle Shielding Properties of Glass Materials Using Analytical Methods and Monte Carlo Simulations	6
MATLAB-Based Modeling and Analysis of Nuclear Power Plant Integration into Ghana’s Electrical Grid: A Dynamic Systems Approach	6
Machine Learning–Based Condition Monitoring of a Circulating Water System of a Canadian Nuclear Plant	6
Evaluating the Validity of a Probabilistic Physics-of-Failure Model with Finite Element Integration for Nuclear Power Plant Piping Reliability	6
Density Equation for Mixed Organic Solutions Containing tri- n -butyl Nitrate, n -Dodecane, Nitric Acid, and Nitrates of Heavy Metals	6
Determination of Gain Scheduling Parameters for Loss of a Feedwater Pump Transient Mitigation Using Neural Networks	6
Training Autonomous Robotic Tasks Through the Use of Machine Learning in Simulated Realities	6
Modeling Flow in a Microreactor Core: From High-Fidelity CFD to Subchannel Analysis	6
Adsorption Properties of Cs(I) and Co(II) on GMZ Bentonite Colloids	6
Development of Emergency Information System to Support Nuclear Power Plant Management in Severe Accident	5
Pressure Drop Correlation Improvement for the Near-Wall Region of Pebble-Bed Reactors	5
Improving Accuracy of a Machine Learning Approach for Forecasting Severe Accidents	5
Iodine Source Term Uncertainty and Sensitivity Analysis with the Severe Accident Code ASTEC: Focus on Iodine Chemistry, Aerosol Behavior, and Containment Pressurization	5
Practitioner-Oriented System Engineering Framework for Nuclear Administrative Processes	5
Adaptive Model Predictive Control for Heat Pipe–Cooled Microreactors Under Normal and Heat Pipe Failure Conditions	5
Radionuclide Transport in Channel Networks with Radial Diffusion in the Porous Rock Matrix	5
Design and Characterization of Y 2 O 3 /Pr 2 O	5

Mobile Application Development Plan for Fire Influence Analysis Using Algebraic Models	5
Acceleration of the Convergence of a Core Thermal-Hydraulic Code Using Initialization from a Neural Network	5
Two Phase Flows in Narrow Rectangular Channels	5
Evaluating Material Attractiveness of Minor Actinide Nuclear Fuel Intended for a Waste Transmutation Lead-Cooled Fast Reactor	5
Development of Early Prediction Model of a CRUD-Induced Power Shift by Applying Autoencoder ML Architecture	5
The Use of High-Density UN Fuel in Heat-Pipe Microreactors	5
Assessing the Structure-Based Turbulence Model Performance for Thermal Striping Applications Using Symmetric Jet Experiments	5
Validation Matrix for Pool Scrubbing Models	5
Foreword: Special Issue Featuring Papers from the 2024 Advanced Reactor Safety Topical Meeting (ARS 2024)	5
Gamma-Ray Spectrometric Investigation of Rare-Earth-Doped Glasses Irradiated by Fast and Thermal Neutrons	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
Effect of Uncertainties in the MSRE Model Salt Properties Using SPECTRA/SUE Analysis	5
Development of Two-Step Method for Fast Chloride MSR Neutronics	5
A RELAP5-3D Model of the Lobo Lead Loop	5
Study of the User Effect Impact in Forward Uncertainty Propagation Approaches Applied to Severe Accident	5
Nuclear Reactor Operations Education and Training with Virtual Reality and an Immersive Desktop Application	5
The Versatile Loop Facility: A New Infrastructure for Testing Components and Systems of Lead Fast Reactor Technology	5
Validation of Axpo’s SIMULATE-3K Model Against Stability Measurements of Leibstadt Nuclear Power Plant	5
Salt Spills Analysis Methodology for KP-FHR: Two-Phase Mechanical Aerosolization and Evaporation Mass Transfer	5
Surveillance Interval Determination for RSG-GAS Components Using Maintenance Priority Index and Weibull–Monte Carlo Simulation: Monitoring of the KLD-BRV10 Generator Set	5
Development and Verification of Neutron Kinetics Parameter Calculation Program Applicable to Subcritical Systems of Long-Life Reactors	5
Safety Benefits Assessment for Accident Tolerant Fuels in Consideration of Steam Generator Tube Degradation Using Dynamic Event Tree Analysis	5
A Multiwire Proportional Chamber for Standardization of Large-Area Sources: Methodology and Challenges for In-House Construction	5
Rationally Designed Core-Shell Structured Fe 3 O 4 @NiFe-LDH Using MIL-100(Fe) as an Intermediate	4
Experiments and CFD for Wire-Wrapped Fuel Assembly Blockages	4
Validation of a Countercurrent Gas Flow Model for Use in the Kairos Power System Analysis Module (KP-SAM) Code	4
Investigation of the Thermal Effects of MgO and ZnO Nanoparticles in a Pressurized Water Reactor Coolant with Computational Fluid Dynamics Model	4
Study of Turbulence and Pressure Recovery in the Heat Pipe Vapor Flow Using the Spectral-Element Method	4
Direct Numerical Simulation and Large Eddy Simulation of a 67-Pebble-Bed Experiment	4
Review of Detecting Anomalies in Power Reactors Using Neutron Noise Analysis	4
Advancing Fixed-Source Reactor Analysis Through OpenNode Implementation	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
2D(r,θ) Simulations of the HBC-4 Power-to-Melt Experiment with the Fuel Performance Code ALCYONE	4
Using Sampler and IRPhE Benchmark Data to Test the Nuclear Data Adjustment Code TSURFER	4
Remark About “Finely Divided Metal as Nuclear Reactor Fuel”	4
Impact of the Uncertainties Associated with Core Degradation in H 2 Production During the In-Vessel Phase	4
Diagnostic Technique Characterizing Neutron Irradiation Effects on Additively Manufactured Inconel 625 Eliminating the Need for Remote Handling	4
Evaluation of Decay Heat Calculation Uncertainties for Spent Fuel from RBMK-1500 Reactor	4
Multiphase Turbulence Modeling Using Sparse Regression and Gene Expression Programming	4
Indirect Parameterized Risk Assessment Applied to Brazilian Nuclear Sector	4
Build-to-Replace Strategy to Reduce Operations and Maintenance Costs for Advanced Reactors	4
Equivalence of the Peierls and Serber Wartime Expressions for the Critical Radius of a Fissile Isotope	4
Is It Time for the United States to Reconsider Transmutation for Spent Nuclear Fuel?	4
Sustaining Nuclear Research Infrastructure in Developing Countries: A Comprehensive Plant Life Extension Strategy for Ghana Research Reactor-1 (GHARR-1), Integrating Technical Assessments, Modernizati	4
Optimization of 89 Zr Production For Immuno-PET Applications	4
Large Eddy Simulation of Low-Reynolds-Number Turbulent Flow of Low-Prandtl-Number Fluid in a Tight Lattice Bundle for Assessment of Reynolds-Averaged Navier-Stokes Turbulence Model	4
Enhancing Site Evaluation Standards for Nuclear Power Plants in Indonesia: Human-Induced External Events	4
Numerical Simulation on Dispersion of Hydrogen Leaked in Particle Layers of Glass Beads and Soil	4
Development of RELAP5-3D Model for an Integrated Test Facility for Advanced Reactor Systems	4
The Experimental and Simulation Results of LIVE-J2 Test—Investigation on Heat Transfer in a Solid–Liquid Mixture Pool	4
Optimizing the Implementation of Small Modular Reactors into Ontario’s Future Energy Mix	4
Discrete Active Disturbance Rejection Control Law Designed for Nuclear Reactor Under Load-Following Operation	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
Assessment of Natural Radionuclide and Radiation Hazard Indices Using Data Analysis and Multivariate Statistical Approach in Duzkoy, Trabzon, Turkey	4
Path Toward a Breeding, Proliferation-Resistant, Thermal-Spectrum Molten Salt Reactor	4
Sparse-View Neutron Computed Tomography 3-D Reconstruction via the Fast Gradient Projection Algorithm	4
Foreword: Special Issue Featuring Selected Papers from the 11th International Topical Meeting on High Temperature Reactor Technology (HTR 2024)	4
Sensitivity Analysis of Transient Critical Heat Flux by RIA Under High-Pressure Flow Boiling Conditions in TRTL	4
Time-Dependent Experiment on Reactor Power Distribution Estimation by Ex-Core Detectors at UTR-KINKI	4
On the Development of a Novel Acoustic Flowmeter for High-Temperature Gas-Cooled Reactors	4
Monte Carlo Perturbation Analysis of Fuel Temperature Variations in the MCNP Model of the Annular Core Research Reactor	4
Availability of the Emergency Safety Electrical System of a Konvoi Nuclear Power Plant Considering Mobile Arrangements of Diesel Generators After Fukushima	4
Validation and Neutronic Analysis of the CENM TRIGA MARK II SCALE Research Reactor Model: Computations Versus Experiment	4
The UO 2 Power-to-Melt Experiment Performed in the High Burnup Chemistry International Program	4
Advanced Autonomous Welding for Refabrication and Follow-On Testing of Previously Irradiated Nuclear Fuel	4
Investigation of the Effects of Low-Energy Photons on Superficial and Sensitive Biological Samples with Geant4 Simulations	4
An Integrated Tool Set for Spent Nuclear Fuel Pool Sabotage Assessment: Coupling DEPO-Based Physical Protection Effectiveness with WSPEEDI Consequence Modeling	4
CFD Modeling of Lead Solidification and Natural Convection in Support of the Westinghouse Lead-Cooled Fast Reactor Development	4
Prospects for Nuclear Microreactors: A Review of the Technology, Economics, and Regulatory Considerations	4
Neutron Energy Spectrum Measurement and Unfolding Method Based on a Single Long Lithium- or Boron-Doped Scintillator	4
Correlation Method of 3-D Detection of Distant Sources of Gamma Radiation and Neutrinos by Intensity Interferometry	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
Impact of Support Properties and Process Parameters on Performance of Supported Liquid Membrane for the Extraction of Uranium from Uranyl Nitrate Pure Solution and Its Mathematical Modeling	3
Technical Reviewers	3
Analysis of Influence of Tube Failure on Performance of Passive Residual Heat Removal Heat Exchanger	3
Entrance Channel–Dependent Quasi-Fission Fragment Distribution	3
MARVEL Microreactor System Thermal-Hydraulic Design and Analysis	3
Magnetic Design and Analysis of a Scanning Magnet for Low-Energy E-beam Sterilization Applications	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
Lead Fast Reactor Thermal-Hydraulic Testing Facilities in Support of the UK Advanced Modular Reactor Program	3
Evaluation of Reaction Rate Distribution Measurement in the Prototype Fast Reactor Monju	3
First Experimental Demonstration of the Use of a Novel Planar Segmented HPGe Detector for Gamma Emission Tomography of Mockup Fuel Rods	3
Exploring the Feasibility of Quantum-Based Secure Communications for Nuclear Applications	3
A Survey of ViBRANT Applied as a MARVEL Closed-Loop Flux and Thermal Surrogate	3
In Situ Chlorine Generation and Rare Earth Chlorination by Molten Salt Electrolysis	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 the P2M Past Fuel Melting Experiments with the Fuel Performance Code FAST-1.0.1	3
Integral-Effect Test for Loss of Residual Heat Removal System During Mid-Loop Operation in ATLAS Facility	3
Extrapolation of Monte Carlo–Derived Noble Gas Air-Submersion Effective Dose Rate Coefficients for Selected Occupational Settings to Other Geometries and Radionuclides	3
Neutronic and Transient Analysis of an Optimized APR-1400 Core Loaded with Accident-Tolerant Fuel and Control Rods Using STREAM/RAST-K 2.0	3
Experimental Performance Evaluation of Miniature Low-Area-Ratio Jet Pumps for High-Temperature Applications	3
Safety Assessment Methodology for Transportation of Radioactive Material via Train	3
Protected Loss-of-Flow Accident in a HLM Pool Facility: Long-Term Cooling Experiment	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
Calculation of Isotope-Specific Fission Rates for Neutrino Source Calculation in PWR Fuel Diversion Safeguarding	3
Preliminary Investigation of Gamma Radiation on the Chemical and Physical Characteristics of an Organic Coolant	3
Comparison of Neutron Radiation Response of Conventionally Wrought Versus Additive Manufacturing Production Methods in Alloy 625	3
Neutronic Analysis of the Conceptual Molten Uranium Breeder Reactor Using MCNP and SCALE Tools	3
Foreword: Special Issue Featuring Papers from the 2023 NEA Rising Stars Workshop	3
Considerations for Hydride Moderator Readiness in Microreactors	3
Development of Multiphase Mixture Model for Simulation of Sodium Aerosol Transport in Cover Gas Space of SFR Systems	3
Application of FSVD Algorithm to Airborne Gamma Detection of Trace Radionuclides in the Process of a High Radon Background	3
Irregular, Backward-Compatible PWR Assembles with More Pins to Facilitate Uprates	3
Application of Systems Usability Case in an Integrated System Validation of Control Room	3
Commentary	3
Research on Consistency Control of Thermal Neutron Sensitivity of Rhodium Self-Powered Neutron Detectors	3
Silicon-Induced Microstructural Refinement in FeCrAl ODS Alloys for Accident-Tolerant Fuel Applications	3
Uncertainty-Aware and Explainable Human Error Detection in the Operation of Nuclear Power Plants	3
High-Accuracy Pulse Shape Discrimination for LSO/LuYAP Crystals Using a CNN-BiLSTM Deep Learning Model	3
Numerical Investigation of Changes in Heat Transfer Coefficient of Water-Aluminum Oxide Nanofluid Cooling in Nuclear Reactors	3
Insights into the Economics of Decarbonizing Maritime Transport with Nuclear Fuel	3
A Study on Boiling Heat Transfer Performance of TiO 2 -CNTs Hybrid Nanofluid on a Downward-Facing Heating Surface	3
Parametric Analysis of Radiological Impact from Hypothetical Accident Scenario at the Sanmen Nuclear Power Plant	3
Analysis of AP1000 Small-Break Loss-of-Coolant Accident Using Reactor Transient Simulator	3
Foreword: Selected papers from the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20)	3
The ENDF/B Nuclear Data Library and Its Impact on Reactor Simulations	3
Human Factors Considerations in Artificial Intelligence Applications for Nuclear Power Plants	2
Numerical Analysis of Heat Pipe Performance Considering Helium Gap Effects	2
Efficient Parallel Computation of Gamma-Ray Dose Fields Using OpenMP and Its Engineering Applications	2
Probabilistic Fracture Analysis for a Boiling Water Reactor Pressure Vessel During Transition to Decommissioning	2
Versatile Testing Facility for Heavy Liquid Metal–Cooled Fast Reactor at the University of Pittsburgh	2
Resilience Governance in Nuclear Safety: Insights from China’s AI-Driven Innovative Practices	2
Development of an Extended State Observer for Monitoring of a PWR Based on a Two-Point Kinetic Model	2
Simulation and Mitigation of False Data Injection Cyberattacks on a Space Nuclear Reactor Power System	2
Constitutive Modeling of Anisotropic Plasticity with ML Algorithms in Metals	2
Comments on the Physics of the Frisch-Peierls Memorandum	2
Multiphysics Analysis of PLOFC and DLOFC Accidents in the HTGR-TR	2
Thorium and Uranium, Specific Surfaces, and Minerals in Bentonites	2
Zombies, Superpowers, and Apocalyptic Narratives: Exploring Science Fiction as a Messy Space for Public Engagement on Radiation, Nuclear Power, and Solving Climate Change	2
A Batch Refueling Framework for Implementing the Sourdough Fuel Cycle and Waste Management Strategy in the EIRENE Novel Molten Salt Reactor Design	2
Digitalization, Management, and Synthesis of Thermal-Hydraulic Legacy Data Using the Dynamical System Scaling	2
Explainable, Deep Reinforcement Learning–Based Decision Making for Operations and Maintenance	2
Effects of Compatibilizers on the Rheological, Thermal, Mechanical, and γ-Ray Shielding Properties of WO 3 /PP Composites	2
i-LAMP: Global, Industrywide Learning Aging Management Program for Neutron-Absorber Materials in Spent Fuel Pools	2
Assessment of Factory Fabrication Considerations for Nuclear Microreactors	2
Pulse Shape Discrimination of Neutrons and Gamma Rays Using Neuromorphic Models	2
Adapting the eVinci Microreactor into a Hybrid Power and Research Reactor Facility for Use at a University Campus	2
Radioisotopes for Nuclear Medicine: An Overview	2
Foreword: Special Issue on Advancements in Uncertainty and Sensitivity Analyses: Current Status and Perspectives	2
Novel Approach for Network Data Exchange Among Safety-Related Control Systems of Nuclear Reactors	2
Formation of Organic Tellurides and Organic Iodides Together Under Gamma Radiation	2
Evaluation of Alternative Safety Cooling Systems for Open Pool Research Reactor with Downward Flow	2
High-Precision Annular Beam Spot Energy Distribution Model and Beam Spot Optimization	2
Direct Numerical Simulation of Single- and Two-Phase Flows for Nuclear Engineering Geometries	2
High-Fidelity Modeling and Experiments to Inform Safety Analysis Codes for Heat Pipe Microreactors	2
Comparative Consequence Analysis for a Heat Pipe–Cooled, TRISO-Fueled Microreactor Operating Across Distinct Climates	2
Glove Operation Compartment with Cuboid Cans for Efficient Handling of Size-Reduced Solid Waste Generated from Plutonium-Contaminated Glovebox Dismantling Activities	2
Development of a Local Pressure Drop Model for Two-Phase Natural Circulation Systems	2
Inferential-Statistical Reevaluation of Spent Fuel Zircaloy Cladding Integrity	2
Evaluation of the New ENDF/B-VIII.0 Nuclear Data Library on Neutronic Parameters Calculations for First Core RSG-GAS Reactor	2
Performance Evaluation of Batchwise Multistage Countercurrent Extraction in a LiCl–KCl/Cd System to Separate Actinides from Rare Earth Fission Products	2
Enhanced Video-Level Anomaly Feature Detection for Nuclear Power Plant Component Inspections Using the Latency Mechanism	2
Optimization of Elliptical U-Tube Heat Exchanger (EUTHE) for Spray Cooling Based on the Taguchi and CFD Method	2
Fuel Fabrication Specification Impact Analysis for NBSR LEU Conversion	2
Thermal Assessment of Repository Footprint Requirement for Advanced Fuel Cycles	2
SAM: A Modern System Code for Advanced Non-LWR Safety Analysis	2
Stability Tests and Analysis of a Low-Pressure Natural Circulation Loop with Flashing Instability	2
Fiberoptic Laser-Induced Breakdown Spectroscopy System for in situ Measurement in a Hazardous Environment	2
Refueling Considerations for 99 Mo Production in a CANDU Reactor	2
Technical Reviewers	2
Research Activities Associated with the Treatment of Potential Common-Cause Failures in Event and Condition Assessments	2
Experimental and Numerical Reassessment of Real-World Defects in Nuclear Components Through Additively Manufactured Physical Twins	2
ENTS: A Novel Algorithm for Sampling-Based Dynamic Probabilistic Risk Assessment	2
Evaluation of Neutron Scattering and Shielding Behavior in Epoxy-hBN Composites for Nuclear Applications	2
Review of Leak Rates and Control in High-Temperature Fluid Applications	2
Scientific and Cultural Heritage in Argentina’s Nuclear Sector: Meanings and Dynamics of Activation at the Bariloche Atomic Center	2
Role of Accelerated Burnup Irradiation Testing in Support of Accelerated Fuel Qualification	2
Advanced Reactor Control and Operations (ARCO): A University Research Facility for Developing Optimized Digital Control Rooms	2
Bayesian Calibration of UO 2 Creep Rates as a Tool for Accelerated Fuel Qualification	2
Technoeconomic Design Optimization for Fast Reactors. Part I: Workflow Development and Case Study for Small LFR District Energy Application	2
Enhanced Boiling Heat Transfer and Critical Heat Flux Characteristics of Fe 3 O 4 Nanofluid Under	2
Improvement of Radiological Waste Characterization with Bayesian Machine Learning	2
Influence of Iodine Chemistry in I 2 Scrubbing Modeling	2