Nuclear Technology

Article	Citations
Thermal-Hydraulic Core Design of a Thorium-Based Molten Salt Fast Energy Amplifier	82
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	29
Spatiotemporal Evaluation of Bubble Characteristics in Sodium Using Real-Time X-Ray Imaging	28
Model Development for Thermal-Hydrology Simulations of a Full-Scale Heater Experiment in Opalinus Clay	28
Availability of Critical Benchmark Experiments for the Pebble Tanker Transportation Model for Nuclear Criticality Safety Validation of TRISO Pebbles	21
FAST Irradiations, Postirradiation Examinations, and Modeling of U-Mo for Light Water Reactor Applications	16
Simulation of a Slow Loss-of-Flow Accident in an Open-Pool Research Reactor Using Computational Fluid Dynamics	16
Risk Plus Some Attributes (R + SA): A New Risk-Informed Method for Prioritizing Inspection Activities During New Fuel Facility Construction	15
Code Validation of SAM Using Forced and Natural Circulation Data from NACIE-UP Benchmark	15
MARVEL Authorization Process	15
Study on Aerosol Deposition Characteristics of an Obstacle Structure During Ventilation for Fukushima Daiichi Decommissioning	13
Assessment of RELAP5-3D Code with Molten Salt Heat Transfer Experiments	13
Long-Lived Fission Products Transmutation in Fission-Free Thermal Accelerator-Driven Transmuter	12
Comprehensive Study on p-n Junction and Schottky Barrier Betavoltaic Battery with 14 C Beta-Emitting Source	12
Neutronics and Thermo-Fluids Simulation of Generic Pebble-Bed Fluoride-Salt-Cooled High-Temperature Reactor	12
Uncertainty Assessment of an iSMR Passive Safety System: Model Lifecycle Management Study Case	12
Interpreting Thermally and Hydrodynamically Controlled Regions in Subcooled Flow Boiling	12
Optimizing Transmission Expansion for Sustainable Energy Integration in Ghana: A Multiscenario Analysis of Nuclear and Renewable Synergies Within the West African Power Pool Framework	12
Verification and Demonstration of One-Dimensional Freezing Model in SAM for Salt-Cooled Reactor Analysis Applications	11
Best Estimate Plus Uncertainty Analysis of Station Blackout Transient in Pool-Type Research Reactor	11
Optimized Synthesis and Evaluation of Composite Beads for Antimony Removal from Acidic Nuclear Reprocessing Effluent	10
The Design and Development of the Process Radiation Monitoring System of the High Temperature Gas-Cooled Reactor (HTGR) in China	10
Safety Classification of Modular HTGRs Based on the IAEA SSG-30 Method	10

Liquid Film Thickness for Gas-Liquid Annular Flow Across Grid Spacer with Vanes in Simple 3 × 3 Rod Bundle Channel	9
Recent 238 Pu Production Activities at Idaho National Laboratory	9
Monte Carlo Analysis of Coolant Stream Impurity Gamma Emissions in Gas-Cooled Fast Reactors	9
Mapping the Hydrogen Economy in Ghana: The Strategic Contribution of Small Modular Reactors	9
Revisiting Mobile Paste Reactor Fuel	8
Methods for Extending the Reactor Core Lifetime of the Canadian Thermal Battery TM	8
Implementation and Demonstration of the Digital Twin Certification System Remote Operations Framework	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
Comparison of Two Methods for Obtaining the Variabilities in a FRAM Model of a Combined Nuclear Facility Project	8
Examination of Deep Learning Algorithm for Nuclear Proliferation Risk Modeling	8
Research on Active Disturbance Rejection Control of Small Modular Reactor Once-Through Steam Generator Based on Differential Evolution Optimization Algorithm	8
Data-Informed Evaluation Framework for Integrated Energy Systems: Insights from Power, Process Heat, and Hydrogen Production Applications	7
FNERCs Software for Fast Neutron Shielding Assessment Based on ENDF/B-VIII.0, ENDF/B-VIII.1, and TENDL Libraries	7
Comparative Study of Raman and EPMA Elemental Mapping of an Unirradiated MOX Sample	7
“Arturo” Nuclear Power Plant and the Technopolitics of Italian Nuclear Decommissioning	7
Development of a Signal Processing Software for Scintillation Detectors and Implementation on an FPGA for Fast Sensing	7
The Origins of Nuclear Expertise: The Formation of Nuclear Engineering Education in the US and Sweden (1950–1979)	7
Effect of Nb Addition on Corrosion Resistance of U-6Zr Alloys	7
Sociotechnical Readiness Level and Natural Language Processing: Tools for Measuring and Managing Societal Acceptance of Nuclear Energy	7
A Structural Design Approach Tailored for the Rapid Preliminary Design of Microreactor Components	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
Comprehensive Study on Gamma-Ray, Neutron, and Charged Particle Shielding Properties of Glass Materials Using Analytical Methods and Monte Carlo Simulations	6
Adsorption Properties of Cs(I) and Co(II) on GMZ Bentonite Colloids	6
Study of the User Effect Impact in Forward Uncertainty Propagation Approaches Applied to Severe Accident	6
Development of Two-Step Method for Fast Chloride MSR Neutronics	6
The Versatile Loop Facility: A New Infrastructure for Testing Components and Systems of Lead Fast Reactor Technology	6
Thermal-Hydraulic Analysis of Inward and Outward Fuel Plate Buckling in a Typical MTR Reactor	6
Detection of Isotopes in Urban Source Search Low-Count Gamma Spectra Using Hopfield Neural Networks	6
MATLAB-Based Modeling and Analysis of Nuclear Power Plant Integration into Ghana’s Electrical Grid: A Dynamic Systems Approach	6
Density Equation for Mixed Organic Solutions Containing tri- n -butyl Nitrate, n -Dodecane, Nitric Acid, and Nitrates of Heavy Metals	6
Explaining System-Level Prognostics with Established Machine Learning Methods	6
Two Phase Flows in Narrow Rectangular Channels	6
Salt Spills Analysis Methodology for KP-FHR: Two-Phase Mechanical Aerosolization and Evaporation Mass Transfer	6
Machine Learning–Based Condition Monitoring of a Circulating Water System of a Canadian Nuclear Plant	6
Modeling Flow in a Microreactor Core: From High-Fidelity CFD to Subchannel Analysis	6
Determination of Gain Scheduling Parameters for Loss of a Feedwater Pump Transient Mitigation Using Neural Networks	6
An Uncertainty Quantification Method for Neutronics Parameters in the Pressurized Water Reactor Core Control System	6
Training Autonomous Robotic Tasks Through the Use of Machine Learning in Simulated Realities	6
Development of Emergency Information System to Support Nuclear Power Plant Management in Severe Accident	6
CHF Enhancement by γ-Fe 2 O 3 Nanofluids with Pool Boiling Condition on a Downward-Facing Plane	6
Design and Characterization of Y 2 O 3 /Pr 2 O	5
Foreword: Special Issue Featuring Papers from the 2024 Advanced Reactor Safety Topical Meeting (ARS 2024)	5
Pressure Drop Correlation Improvement for the Near-Wall Region of Pebble-Bed Reactors	5
Iodine Source Term Uncertainty and Sensitivity Analysis with the Severe Accident Code ASTEC: Focus on Iodine Chemistry, Aerosol Behavior, and Containment Pressurization	5
Safety Benefits Assessment for Accident Tolerant Fuels in Consideration of Steam Generator Tube Degradation Using Dynamic Event Tree Analysis	5
Improving Accuracy of a Machine Learning Approach for Forecasting Severe Accidents	5
A Multiwire Proportional Chamber for Standardization of Large-Area Sources: Methodology and Challenges for In-House Construction	5
Assessment of Natural Radionuclide and Radiation Hazard Indices Using Data Analysis and Multivariate Statistical Approach in Duzkoy, Trabzon, Turkey	5
Development and Verification of Neutron Kinetics Parameter Calculation Program Applicable to Subcritical Systems of Long-Life Reactors	5

Gamma-Ray Spectrometric Investigation of Rare-Earth-Doped Glasses Irradiated by Fast and Thermal Neutrons	5
Systematic Component Investigation of the Steady-State High-Temperature In-Pile Nuclear Thermal Propulsion Experimental Test Bed	5
Validation Matrix for Pool Scrubbing Models	5
The Use of High-Density UN Fuel in Heat-Pipe Microreactors	5
Evaluating Material Attractiveness of Minor Actinide Nuclear Fuel Intended for a Waste Transmutation Lead-Cooled Fast Reactor	5
Adaptive Model Predictive Control for Heat Pipe–Cooled Microreactors Under Normal and Heat Pipe Failure Conditions	5
Heat Transfer Analysis of Core Melt Contact with a CANDU Calandria	5
Mobile Application Development Plan for Fire Influence Analysis Using Algebraic Models	5
Direct Numerical Simulation and Large Eddy Simulation of a 67-Pebble-Bed Experiment	5
Study of Turbulence and Pressure Recovery in the Heat Pipe Vapor Flow Using the Spectral-Element Method	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
Radionuclide Transport in Channel Networks with Radial Diffusion in the Porous Rock Matrix	5
Assessing the Structure-Based Turbulence Model Performance for Thermal Striping Applications Using Symmetric Jet Experiments	5
Practitioner-Oriented System Engineering Framework for Nuclear Administrative Processes	5
Nuclear Reactor Operations Education and Training with Virtual Reality and an Immersive Desktop Application	5
A RELAP5-3D Model of the Lobo Lead Loop	5
Development of Early Prediction Model of a CRUD-Induced Power Shift by Applying Autoencoder ML Architecture	5
Validation of a Hybrid Domain Overlapping Coupling Between SAM and CFD Against the TALL-3D Transients	5
Sustaining Nuclear Research Infrastructure in Developing Countries: A Comprehensive Plant Life Extension Strategy for Ghana Research Reactor-1 (GHARR-1), Integrating Technical Assessments, Modernizati	5
Validation of Axpo’s SIMULATE-3K Model Against Stability Measurements of Leibstadt Nuclear Power Plant	5
Prognostics and Health Management for Maintenance-Dependent Processes	5
Time-Dependent Experiment on Reactor Power Distribution Estimation by Ex-Core Detectors at UTR-KINKI	4
A Study on Boiling Heat Transfer Performance of TiO 2 -CNTs Hybrid Nanofluid on a Downward-Facing Heating Surface	4
Optimizing the Implementation of Small Modular Reactors into Ontario’s Future Energy Mix	4
Investigation of the Thermal Effects of MgO and ZnO Nanoparticles in a Pressurized Water Reactor Coolant with Computational Fluid Dynamics Model	4
Indirect Parameterized Risk Assessment Applied to Brazilian Nuclear Sector	4
Multiphase Turbulence Modeling Using Sparse Regression and Gene Expression Programming	4
Numerical Simulation on Dispersion of Hydrogen Leaked in Particle Layers of Glass Beads and Soil	4
Prospects for Nuclear Microreactors: A Review of the Technology, Economics, and Regulatory Considerations	4
Sparse-View Neutron Computed Tomography 3-D Reconstruction via the Fast Gradient Projection Algorithm	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
Path Toward a Breeding, Proliferation-Resistant, Thermal-Spectrum Molten Salt Reactor	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
Advancing Fixed-Source Reactor Analysis Through OpenNode Implementation	4
Remark About “Finely Divided Metal as Nuclear Reactor Fuel”	4
Availability of the Emergency Safety Electrical System of a Konvoi Nuclear Power Plant Considering Mobile Arrangements of Diesel Generators After Fukushima	4
2D(r,θ) Simulations of the HBC-4 Power-to-Melt Experiment with the Fuel Performance Code ALCYONE	4
Evaluation of Reaction Rate Distribution Measurement in the Prototype Fast Reactor Monju	4
On the Development of a Novel Acoustic Flowmeter for High-Temperature Gas-Cooled Reactors	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
Validation and Neutronic Analysis of the CENM TRIGA MARK II SCALE Research Reactor Model: Computations Versus Experiment	4
Experiments and CFD for Wire-Wrapped Fuel Assembly Blockages	4
CFD Modeling of Lead Solidification and Natural Convection in Support of the Westinghouse Lead-Cooled Fast Reactor Development	4
Diagnostic Technique Characterizing Neutron Irradiation Effects on Additively Manufactured Inconel 625 Eliminating the Need for Remote Handling	4
Foreword: Special Issue Featuring Selected Papers from the 11th International Topical Meeting on High Temperature Reactor Technology (HTR 2024)	4
Rationally Designed Core-Shell Structured Fe 3 O 4 @NiFe-LDH Using MIL-100(Fe) as an Intermediate	4
Validation of a Countercurrent Gas Flow Model for Use in the Kairos Power System Analysis Module (KP-SAM) Code	4
Sensitivity Analysis of Transient Critical Heat Flux by RIA Under High-Pressure Flow Boiling Conditions in TRTL	4
Neutron Energy Spectrum Measurement and Unfolding Method Based on a Single Long Lithium- or Boron-Doped Scintillator	4
Application of FSVD Algorithm to Airborne Gamma Detection of Trace Radionuclides in the Process of a High Radon Background	4
Review of Detecting Anomalies in Power Reactors Using Neutron Noise Analysis	4
Advanced Autonomous Welding for Refabrication and Follow-On Testing of Previously Irradiated Nuclear Fuel	4
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	4
Enhancing Site Evaluation Standards for Nuclear Power Plants in Indonesia: Human-Induced External Events	4
Comparison of Neutron Radiation Response of Conventionally Wrought Versus Additive Manufacturing Production Methods in Alloy 625	4
Evaluation of Decay Heat Calculation Uncertainties for Spent Fuel from RBMK-1500 Reactor	4
Monte Carlo Perturbation Analysis of Fuel Temperature Variations in the MCNP Model of the Annular Core Research Reactor	4
An Integrated Tool Set for Spent Nuclear Fuel Pool Sabotage Assessment: Coupling DEPO-Based Physical Protection Effectiveness with WSPEEDI Consequence Modeling	4
Equivalence of the Peierls and Serber Wartime Expressions for the Critical Radius of a Fissile Isotope	4
The UO 2 Power-to-Melt Experiment Performed in the High Burnup Chemistry International Program	4
Foreword: Special issue on the Nuclear Energy Advanced Modeling and Simulation Thermal Hydraulics Integrated Research Project	4
Build-to-Replace Strategy to Reduce Operations and Maintenance Costs for Advanced Reactors	4
Is It Time for the United States to Reconsider Transmutation for Spent Nuclear Fuel?	4
Impact of the Uncertainties Associated with Core Degradation in H 2 Production during the In-Vessel Phase	4
Discrete Element Method Simulation of the Idaho Calcine Simulant for Hot Isostatic Pressing Canister Filling Process: Part 2	4
Exploring the Feasibility of Quantum-Based Secure Communications for Nuclear Applications	4
The Experimental and Simulation Results of LIVE-J2 Test—Investigation on Heat Transfer in a Solid–Liquid Mixture Pool	4
Discrete Active Disturbance Rejection Control Law Designed for Nuclear Reactor Under Load-Following Operation	4
Development of RELAP5-3D Model for an Integrated Test Facility for Advanced Reactor Systems	4
Insights into the Economics of Decarbonizing Maritime Transport with Nuclear Fuel	4
Calculation of Isotope-Specific Fission Rates for Neutrino Source Calculation in PWR Fuel Diversion Safeguarding	3
The ENDF/B Nuclear Data Library and Its Impact on Reactor Simulations	3
Experimental Performance Evaluation of Miniature Low-Area-Ratio Jet Pumps for High-Temperature Applications	3
Silicon-Induced Microstructural Refinement in FeCrAl ODS Alloys for Accident-Tolerant Fuel Applications	3
Radiation Shielding for Electronic Cards Produced for Use on Cube Satellites	3
A High-Temperature Gas-Cooled Reactor to Directly Reuse Spent Fuel: Analyzing the Effects on Core Performance Caused by Simple Core Modifications	3
Correlation Method of 3-D Detection of Distant Sources of Gamma Radiation and Neutrinos by Intensity Interferometry	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
Integral-Effect Test for Loss of Residual Heat Removal System During Mid-Loop Operation in ATLAS Facility	3
First Experimental Demonstration of the Use of a Novel Planar Segmented HPGe Detector for Gamma Emission Tomography of Mockup Fuel Rods	3

Extrapolation of Monte Carlo–Derived Noble Gas Air-Submersion Effective Dose Rate Coefficients for Selected Occupational Settings to Other Geometries and Radionuclides	3
Development of Multiphase Mixture Model for Simulation of Sodium Aerosol Transport in Cover Gas Space of SFR Systems	3
Entrance Channel–Dependent Quasi-Fission Fragment Distribution	3
High-Accuracy Pulse Shape Discrimination for LSO/LuYAP Crystals Using a CNN-BiLSTM Deep Learning Model	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
A Survey of ViBRANT Applied as a MARVEL Closed-Loop Flux and Thermal Surrogate	3
Uncertainty-Aware and Explainable Human Error Detection in the Operation of Nuclear Power Plants	3
Thermal-Hydraulic Behavior and Safety Characteristics of the NHR200-II Reactor During Small-Break Loss-of-Coolant Accidents	3
Computational Framework for Estimating Cost of Equipment Disposal for Advanced Reactors	3
Lightweight Heat Pipe Radiator for Nuclear Reactor Power Systems on Lunar Surface	3
Techniques for Sensitivity Analysis in Severe Accidents: A Comparative Study	3
Experimental Validation of Modeling and Simulation Capabilities of RELAP5-TMSR with the NNCL Experimental Facility	3
Analysis of Influence of Tube Failure on Performance of Passive Residual Heat Removal Heat Exchanger	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
Application of Systems Usability Case in an Integrated System Validation of Control Room	3
Parametric Analysis of Radiological Impact from Hypothetical Accident Scenario at the Sanmen Nuclear Power Plant	3
Modeling of the P2M Past Fuel Melting Experiments with the Fuel Performance Code FAST-1.0.1	3
In Situ Chlorine Generation and Rare Earth Chlorination by Molten Salt Electrolysis	3
Foreword: Special Issue Featuring Papers from the 2023 NEA Rising Stars Workshop	3
Protected Loss-of-Flow Accident in a HLM Pool Facility: Long-Term Cooling Experiment	3
Magnetic Design and Analysis of a Scanning Magnet for Low-Energy E-beam Sterilization Applications	3
Considerations for Hydride Moderator Readiness in Microreactors	3
Neutronic Analysis of the Conceptual Molten Uranium Breeder Reactor Using MCNP and SCALE Tools	3
Commentary	3
Correction	3
Integrating Econometrics and Artificial Intelligence to Assess the Impact of Trade on Nuclear Proliferation	3
Foreword: Selected papers from the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20)	3
Irregular, Backward-Compatible PWR Assembles with More Pins to Facilitate Uprates	3
Advanced Reactor Control and Operations (ARCO): A University Research Facility for Developing Optimized Digital Control Rooms	3
Numerical Investigation of Changes in Heat Transfer Coefficient of Water-Aluminum Oxide Nanofluid Cooling in Nuclear Reactors	3
Technical Reviewers	3
Safety Assessment Methodology for Transportation of Radioactive Material via Train	3
Preliminary Investigation of Gamma Radiation on the Chemical and Physical Characteristics of an Organic Coolant	3
Lead Fast Reactor Thermal-Hydraulic Testing Facilities in Support of the UK Advanced Modular Reactor Program	3
Analysis of AP1000 Small-Break Loss-of-Coolant Accident Using Reactor Transient Simulator	3
UaSA Application in Severe Accident Analysis: Challenges and Path Forward	2
Development of an Extended State Observer for Monitoring of a PWR Based on a Two-Point Kinetic Model	2
Thorium and Uranium, Specific Surfaces, and Minerals in Bentonites	2
Comments on the Physics of the Frisch-Peierls Memorandum	2
A Batch Refueling Framework for Implementing the Sourdough Fuel Cycle and Waste Management Strategy in the EIRENE Novel Molten Salt Reactor Design	2
Foreword Special Issue on Advancements in Uncertainty and Sensitivity Analyses: Current Status and Perspectives	2
Experimental and Numerical Reassessment of Real-World Defects in Nuclear Components Through Additively Manufactured Physical Twins	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
Simulation and Mitigation of False Data Injection Cyberattacks on a Space Nuclear Reactor Power System	2
Scientific and Cultural Heritage in Argentina’s Nuclear Sector: Meanings and Dynamics of Activation at the Bariloche Atomic Center	2
Radioisotopes for Nuclear Medicine: An Overview	2
Benchmarking Neutron Counting System for Passive Measurements and Active Interrogation of Unknown Objects for Fissile and Fissionable Materials Determination	2
Review of Leak Rates and Control in High-Temperature Fluid Applications	2
Localization of Stationary and Moving Radiation Sources Using a Feedforward Neural Network with an Array of Sensors	2
Developing a Three-Dimensional Bubble Dynamics Model for Centrifugal Nuclear Thermal Propulsion	2
Exploring the Feasibility of Kuiper Belt Missions Supported by Centrifugal Nuclear Thermal Propulsion	2
Multiphysics Analysis of PLOFC and DLOFC Accidents in the HTGR-TR	2
Exploring Public Discourse About Spent Nuclear Fuel Management on Twitter	2
Formation of Organic Tellurides and Organic Iodides Together Under Gamma Radiation	2
Startup and Multiphysics Analysis of a Compact kW-Class Thermal Spectrum Microreactor	2
Adapting the eVinci Microreactor into a Hybrid Power and Research Reactor Facility for Use at a University Campus	2
Direct Numerical Simulation of Single- and Two-Phase Flows for Nuclear Engineering Geometries	2
Detecting Anomalies in Simulated Nuclear Data Using Autoencoders	2
Comparative Consequence Analysis for a Heat Pipe–Cooled, TRISO-Fueled Microreactor Operating Across Distinct Climates	2
Simplified Reactor Model for Microreactor Coupled with Helium Closed Brayton Cycle	2
Assessment of Factory Fabrication Considerations for Nuclear Microreactors	2
High-Fidelity Modeling and Experiments to Inform Safety Analysis Codes for Heat Pipe Microreactors	2
Fuel Fabrication Specification Impact Analysis for NBSR LEU Conversion	2
Glove Operation Compartment with Cuboid Cans for Efficient Handling of Size-Reduced Solid Waste Generated from Plutonium-Contaminated Glovebox Dismantling Activities	2
Thermal Assessment of Repository Footprint Requirement for Advanced Fuel Cycles	2
Development of a Local Pressure Drop Model for Two-Phase Natural Circulation Systems	2
Stability Tests and Analysis of a Low-Pressure Natural Circulation Loop with Flashing Instability	2
Analytical Model of Natural Circulation with a Sinusoidal Heat Input in a PWR	2
Design of Moderator Assemblies for Fast, Epithermal, or Thermal Neutron–Dominated n-γ Mixed Fields Using a D-D Neutron Source	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
Experimental Model to Study Characteristics of Radon Cover in Waste Landfills	2
Influence of Iodine Chemistry in I 2 Scrubbing Modeling	2
High-Fidelity Velocity and Concentration Measurements of Turbulent Buoyant Jets	2
Automatic Generation of Event Trees and Fault Trees: A Model-Based Approach	2
Technical Reviewers	2
Constitutive Modeling of Anisotropic Plasticity with ML Algorithms in Metals	2
ENTS: A Novel Algorithm for Sampling-Based Dynamic Probabilistic Risk Assessment	2
Resilience Governance in Nuclear Safety: Insights from China’s AI-Driven Innovative Practices	2
Human Factors Considerations in Artificial Intelligence Applications for Nuclear Power Plants	2
Bayesian Calibration of UO 2 Creep Rates as a Tool for Accelerated Fuel Qualification	2
Versatile Testing Facility for Heavy Liquid Metal–Cooled Fast Reactor at the University of Pittsburgh	2
Evaluation of Neutron Scattering and Shielding Behavior in Epoxy-hBN Composites for Nuclear Applications	2
Inferential-Statistical Reevaluation of Spent Fuel Zircaloy Cladding Integrity	2
Research Activities Associated with the Treatment of Potential Common-Cause Failures in Event and Condition Assessments	2
Numerical Analysis of Heat Pipe Performance Considering Helium Gap Effects	2
Role of Accelerated Burnup Irradiation Testing in Support of Accelerated Fuel Qualification	2
Probabilistic Fracture Analysis for a Boiling Water Reactor Pressure Vessel During Transition to Decommissioning	2
Toward a Better Understanding of Reflood Thermal Hydraulics: A Summary of the OECD/NEA RBHT Project	2
Design and Suitability Analysis of FPGA-Based TCP/IP Offload Module for Control Systems of FBRs	2
Lumped Parameter Analysis of Autogenous Propellant Pressurization System for Nuclear Thermal Rocket	2
Refueling Considerations for 99 Mo Production in a CANDU Reactor	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
Advanced Instrumentation and Modeling Framework for Two-Phase Flow	2