Nuclear Technology

Article	Citations
Thermal-Hydraulic Core Design of a Thorium-Based Molten Salt Fast Energy Amplifier	76
Verification and Demonstration of One-Dimensional Freezing Model in SAM for Salt-Cooled Reactor Analysis Applications	41
STORAGE: A Source Term Model for Intermediate-Level Radioactive Waste	29
Safety Classification of Modular HTGRs Based on the IAEA SSG-30 Method	28
Validation of Pronghorn Pressure Drop Correlations Against Pebble Bed Experiments	28
An Anisotropic Neutron Collimating System for Proton Accelerator–Generated Secondary Particles	27
Spatiotemporal Evaluation of Bubble Characteristics in Sodium Using Real-Time X-Ray Imaging	26
Best Estimate Plus Uncertainty Analysis of Station Blackout Transient in Pool-Type Research Reactor	19
Model Development for Thermal-Hydrology Simulations of a Full-Scale Heater Experiment in Opalinus Clay	18
Availability of Critical Benchmark Experiments for the Pebble Tanker Transportation Model for Nuclear Criticality Safety Validation of TRISO Pebbles	15
Mapping the Hydrogen Economy in Ghana: The Strategic Contribution of Small Modular Reactors	14
Interpreting Thermally and Hydrodynamically Controlled Regions in Subcooled Flow Boiling	14
Comprehensive Study on p-n Junction and Schottky Barrier Betavoltaic Battery with 14 C Beta-Emitting Source	13
FAST Irradiations, Postirradiation Examinations, and Modeling of U-Mo for Light Water Reactor Applications	13
The Design and Development of the Process Radiation Monitoring System of the High Temperature Gas-Cooled Reactor (HTGR) in China	13
Simulation of a Slow Loss-of-Flow Accident in an Open-Pool Research Reactor Using Computational Fluid Dynamics	13
Code Validation of SAM Using Forced and Natural Circulation Data from NACIE-UP Benchmark	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
MARVEL Authorization Process	12
Uncertainty Assessment of an iSMR Passive Safety System: Model Lifecycle Management Study Case	11
Study on Aerosol Deposition Characteristics of an Obstacle Structure During Ventilation for Fukushima Daiichi Decommissioning	11
Neutronics and Thermo-Fluids Simulation of Generic Pebble-Bed Fluoride-Salt-Cooled High-Temperature Reactor	11
Long-Lived Fission Products Transmutation in Fission-Free Thermal Accelerator-Driven Transmuter	11
Assessment of RELAP5-3D Code with Molten Salt Heat Transfer Experiments	11
Nuclear Power Concepts and Development Strategies for High-Power Electric Propulsion Missions to Mars	11

Monte Carlo Analysis of Coolant Stream Impurity Gamma Emissions in Gas-Cooled Fast Reactors	10
Risk Plus Some Attributes (R + SA): A New Risk-Informed Method for Prioritizing Inspection Activities During New Fuel Facility Construction	10
Liquid Film Thickness for Gas-Liquid Annular Flow Across Grid Spacer with Vanes in Simple 3 × 3 Rod Bundle Channel	10
Recent 238 Pu Production Activities at Idaho National Laboratory	10
Fluid Dynamics Effects of a Porous Blockage on Laminar Flow in the Interior Subchannels of a 61-Pin Wire-Wrapped Rod Bundle	9
Network Graph Laplacian-Based Sensor Projection in System-Level Modeling of Liquid-Metal Loop	9
Revisiting Mobile Paste Reactor Fuel	9
Comparison of Two Methods for Obtaining the Variabilities in a FRAM Model of a Combined Nuclear Facility Project	8
Comprehensive Study on Gamma-Ray, Neutron, and Charged Particle Shielding Properties of Glass Materials Using Analytical Methods and Monte Carlo Simulations	8
Detection of Isotopes in Urban Source Search Low-Count Gamma Spectra Using Hopfield Neural Networks	8
Examination of Deep Learning Algorithm for Nuclear Proliferation Risk Modeling	8
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	8
Methods for Extending the Reactor Core Lifetime of the Canadian Thermal Battery TM	8
Research on Active Disturbance Rejection Control of Small Modular Reactor Once-Through Steam Generator Based on Differential Evolution Optimization Algorithm	7
“Arturo” Nuclear Power Plant and the Technopolitics of Italian Nuclear Decommissioning	7
Adsorption Properties of Cs(I) and Co(II) on GMZ Bentonite Colloids	7
MATLAB-Based Modeling and Analysis of Nuclear Power Plant Integration into Ghana’s Electrical Grid: A Dynamic Systems Approach	7
Implementation and Demonstration of the Digital Twin Certification System Remote Operations Framework	7
Effect of Nb Addition on Corrosion Resistance of U-6Zr Alloys	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
Sociotechnical Readiness Level and Natural Language Processing: Tools for Measuring and Managing Societal Acceptance of Nuclear Energy	6
Thermal-Hydraulic Analysis of Inward and Outward Fuel Plate Buckling in a Typical MTR Reactor	6
Improving Accuracy of a Machine Learning Approach for Forecasting Severe Accidents	6
Explaining System-Level Prognostics with Established Machine Learning Methods	6
The Versatile Loop Facility: A New Infrastructure for Testing Components and Systems of Lead Fast Reactor Technology	6
The Origins of Nuclear Expertise: The Formation of Nuclear Engineering Education in the US and Sweden (1950–1979)	6
Comparative Study of Raman and EPMA Elemental Mapping of an Unirradiated MOX Sample	6
A Structural Design Approach Tailored for the Rapid Preliminary Design of Microreactor Components	6
Validation Matrix for Pool Scrubbing Models	6
Development of Emergency Information System to Support Nuclear Power Plant Management in Severe Accident	6
Training Autonomous Robotic Tasks Through the Use of Machine Learning in Simulated Realities	6
Determination of Gain Scheduling Parameters for Loss of a Feedwater Pump Transient Mitigation Using Neural Networks	6
Organic Telluride Formation from Paint Solvents Under Gamma Irradiation	6
A RELAP5-3D Model of the Lobo Lead Loop	6
Density Equation for Mixed Organic Solutions Containing tri- n -butyl Nitrate, n -Dodecane, Nitric Acid, and Nitrates of Heavy Metals	6
Study of the User Effect Impact in Forward Uncertainty Propagation Approaches Applied to Severe Accident	6
Evaluating Material Attractiveness of Minor Actinide Nuclear Fuel Intended for a Waste Transmutation Lead-Cooled Fast Reactor	6
CHF Enhancement by γ-Fe 2 O 3 Nanofluids with Pool Boiling Condition on a Downward-Facing Plane	6
FNERCs Software for Fast Neutron Shielding Assessment Based on ENDF/B-VIII.0, ENDF/B-VIII.1, and TENDL Libraries	6
Development of Two-Step Method for Fast Chloride MSR Neutronics	5
The Use of High-Density UN Fuel in Heat-Pipe Microreactors	5
Build-to-Replace Strategy to Reduce Operations and Maintenance Costs for Advanced Reactors	5
Validation of a Hybrid Domain Overlapping Coupling Between SAM and CFD Against the TALL-3D Transients	5
Study of Turbulence and Pressure Recovery in the Heat Pipe Vapor Flow Using the Spectral-Element Method	5
Effect of Nozzle Diameter on Quenching Behavior of Simulant Material CaO-Fe2O3 Under Bottom Flooding Conditions	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
Safety Benefits Assessment for Accident Tolerant Fuels in Consideration of Steam Generator Tube Degradation Using Dynamic Event Tree Analysis	5
Prognostics and Health Management for Maintenance-Dependent Processes	5
Validation of Axpo’s SIMULATE-3K Model Against Stability Measurements of Leibstadt Nuclear Power Plant	5

Foreword: Special Issue Featuring Papers from the 2024 Advanced Reactor Safety Topical Meeting (ARS 2024)	5
A Multiwire Proportional Chamber for Standardization of Large-Area Sources: Methodology and Challenges for In-House Construction	5
Development and Verification of Neutron Kinetics Parameter Calculation Program Applicable to Subcritical Systems of Long-Life Reactors	5
Assessment of Natural Radionuclide and Radiation Hazard Indices Using Data Analysis and Multivariate Statistical Approach in Duzkoy, Trabzon, Turkey	5
Mobile Application Development Plan for Fire Influence Analysis Using Algebraic Models	5
Multiphase Turbulence Modeling Using Sparse Regression and Gene Expression Programming	5
Heat Transfer Analysis of Core Melt Contact with a CANDU Calandria	5
Direct Numerical Simulation and Large Eddy Simulation of a 67-Pebble-Bed Experiment	5
Adaptive Model Predictive Control for Heat Pipe–Cooled Microreactors Under Normal and Heat Pipe Failure Conditions	5
Design and Characterization of Y 2 O 3 /Pr 2 O	5
Iodine Source Term Uncertainty and Sensitivity Analysis with the Severe Accident Code ASTEC: Focus on Iodine Chemistry, Aerosol Behavior, and Containment Pressurization	5
Salt Spills Analysis Methodology for KP-FHR: Two-Phase Mechanical Aerosolization and Evaporation Mass Transfer	5
Nuclear Reactor Operations Education and Training with Virtual Reality and an Immersive Desktop Application	5
Gamma-Ray Spectrometric Investigation of Rare-Earth-Doped Glasses Irradiated by Fast and Thermal Neutrons	5
Is It Time for the United States to Reconsider Transmutation for Spent Nuclear Fuel?	5
Pressure Drop Correlation Improvement for the Near-Wall Region of Pebble-Bed Reactors	5
Sensitivity Analysis of Transient Critical Heat Flux by RIA Under High-Pressure Flow Boiling Conditions in TRTL	5
Assessing the Structure-Based Turbulence Model Performance for Thermal Striping Applications Using Symmetric Jet Experiments	5
Radionuclide Transport in Channel Networks with Radial Diffusion in the Porous Rock Matrix	5
Systematic Component Investigation of the Steady-State High-Temperature In-Pile Nuclear Thermal Propulsion Experimental Test Bed	5
Modal Decomposition of the Flow in a Randomly Packed Pebble Bed with Direct Numerical Simulation	4
Comment on Comparison Between Historic Nuclear Explosion Yield Formulas	4
Path Toward a Breeding, Proliferation-Resistant, Thermal-Spectrum Molten Salt Reactor	4
The UO 2 Power-to-Melt Experiment Performed in the High Burnup Chemistry International Program	4
Evaluation of Decay Heat Calculation Uncertainties for Spent Fuel from RBMK-1500 Reactor	4
Optimizing the Implementation of Small Modular Reactors into Ontario’s Future Energy Mix	4
Enhancing Site Evaluation Standards for Nuclear Power Plants in Indonesia: Human-Induced External Events	4
Impact of the Uncertainties Associated with Core Degradation in H 2 Production during the In-Vessel Phase	4
Development of RELAP5-3D Model for an Integrated Test Facility for Advanced Reactor Systems	4
Foreword: Special issue on the Nuclear Energy Advanced Modeling and Simulation Thermal Hydraulics Integrated Research Project	4
Rationally Designed Core-Shell Structured Fe 3 O 4 @NiFe-LDH Using MIL-100(Fe) as an Intermediate	4
Diagnostic Technique Characterizing Neutron Irradiation Effects on Additively Manufactured Inconel 625 Eliminating the Need for Remote Handling	4
Remark About “Finely Divided Metal as Nuclear Reactor Fuel”	4
Discrete Element Method Simulation of the Idaho Calcine Simulant for Hot Isostatic Pressing Canister Filling Process: Part 2	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
On the Development of a Novel Acoustic Flowmeter for High-Temperature Gas-Cooled Reactors	4
Equivalence of the Peierls and Serber Wartime Expressions for the Critical Radius of a Fissile Isotope	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
Validation and Neutronic Analysis of the CENM TRIGA MARK II SCALE Research Reactor Model: Computations Versus Experiment	4
2D(r,θ) Simulations of the HBC-4 Power-to-Melt Experiment with the Fuel Performance Code ALCYONE	4
Sparse-View Neutron Computed Tomography 3-D Reconstruction via the Fast Gradient Projection Algorithm	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
CFD Modeling of Lead Solidification and Natural Convection in Support of the Westinghouse Lead-Cooled Fast Reactor Development	4
The Experimental and Simulation Results of LIVE-J2 Test—Investigation on Heat Transfer in a Solid–Liquid Mixture Pool	4
Neutron Energy Spectrum Measurement and Unfolding Method Based on a Single Long Lithium- or Boron-Doped Scintillator	4
Time-Dependent Experiment on Reactor Power Distribution Estimation by Ex-Core Detectors at UTR-KINKI	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
Experiments and CFD for Wire-Wrapped Fuel Assembly Blockages	4
Investigation of the Thermal Effects of MgO and ZnO Nanoparticles in a Pressurized Water Reactor Coolant with Computational Fluid Dynamics Model	4
Validation of a Countercurrent Gas Flow Model for Use in the Kairos Power System Analysis Module (KP-SAM) Code	4
Prospects for Nuclear Microreactors: A Review of the Technology, Economics, and Regulatory Considerations	4
Indirect Parameterized Risk Assessment Applied to Brazilian Nuclear Sector	4
Neutronic Analysis of the Conceptual Molten Uranium Breeder Reactor Using MCNP and SCALE Tools	3
Correction	3
Calculation of Isotope-Specific Fission Rates for Neutrino Source Calculation in PWR Fuel Diversion Safeguarding	3
Advanced Reactor Control and Operations (ARCO): A University Research Facility for Developing Optimized Digital Control Rooms	3
Availability of the Emergency Safety Electrical System of a Konvoi Nuclear Power Plant Considering Mobile Arrangements of Diesel Generators After Fukushima	3
In Situ Chlorine Generation and Rare Earth Chlorination by Molten Salt Electrolysis	3
Insights into the Economics of Decarbonizing Maritime Transport with Nuclear Fuel	3
First Experimental Demonstration of the Use of a Novel Planar Segmented HPGe Detector for Gamma Emission Tomography of Mockup Fuel Rods	3
Modeling of Lateral Flow in CFD for Subchannel Analysis	3
Application of Systems Usability Case in an Integrated System Validation of Control Room	3
Experimental Performance Evaluation of Miniature Low-Area-Ratio Jet Pumps for High-Temperature Applications	3
Uncertainty-Aware and Explainable Human Error Detection in the Operation of Nuclear Power Plants	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
Discrete Active Disturbance Rejection Control Law Designed for Nuclear Reactor Under Load-Following Operation	3
Numerical Investigation of Changes in Heat Transfer Coefficient of Water-Aluminum Oxide Nanofluid Cooling in Nuclear Reactors	3
Study on Flow Characteristics of Integrated Natural Circulation Reactor Under Inclined Conditions	3
Modeling of the P2M Past Fuel Melting Experiments with the Fuel Performance Code FAST-1.0.1	3
Lightweight Heat Pipe Radiator for Nuclear Reactor Power Systems on Lunar Surface	3
Lead Fast Reactor Thermal-Hydraulic Testing Facilities in Support of the UK Advanced Modular Reactor Program	3
Radiation Shielding for Electronic Cards Produced for Use on Cube Satellites	3
A Study on Boiling Heat Transfer Performance of TiO 2 -CNTs Hybrid Nanofluid on a Downward-Facing Heating Surface	3
Analysis of Influence of Tube Failure on Performance of Passive Residual Heat Removal Heat Exchanger	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
Parametric Analysis of Radiological Impact from Hypothetical Accident Scenario at the Sanmen Nuclear Power Plant	3
Evaluation of Reaction Rate Distribution Measurement in the Prototype Fast Reactor Monju	3
Extrapolation of Monte Carlo–Derived Noble Gas Air-Submersion Effective Dose Rate Coefficients for Selected Occupational Settings to Other Geometries and Radionuclides	3
Exploring the Feasibility of Quantum-Based Secure Communications for Nuclear Applications	3

Numerical Simulation on Dispersion of Hydrogen Leaked in Particle Layers of Glass Beads and Soil	3
Integral-Effect Test for Loss of Residual Heat Removal System During Mid-Loop Operation in ATLAS Facility	3
Protected Loss-of-Flow Accident in a HLM Pool Facility: Long-Term Cooling Experiment	3
Preliminary Investigation of Gamma Radiation on the Chemical and Physical Characteristics of an Organic Coolant	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
Safety Assessment Methodology for Transportation of Radioactive Material via Train	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
Impact of Steel Equipment on Cyclotron Activation and Its Implications for Radioactive Waste Management	3
Irregular, Backward-Compatible PWR Assembles with More Pins to Facilitate Uprates	3
Magnetic Design and Analysis of a Scanning Magnet for Low-Energy E-beam Sterilization Applications	3
Presentation of the xM3 Test Case of the P2M Simulation Exercise and Modeling with the Fuel Performance Code ALCYONE	3
Advancing Fixed-Source Reactor Analysis Through OpenNode Implementation	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
Application of FSVD Algorithm to Airborne Gamma Detection of Trace Radionuclides in the Process of a High Radon Background	3
Silicon-Induced Microstructural Refinement in FeCrAl ODS Alloys for Accident-Tolerant Fuel Applications	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
Foreword: Special Issue Featuring Papers from the 2023 NEA Rising Stars Workshop	3
Comparison of Neutron Radiation Response of Conventionally Wrought Versus Additive Manufacturing Production Methods in Alloy 625	3
Technical Reviewers	3
Considerations for Hydride Moderator Readiness in Microreactors	3
Monte Carlo Perturbation Analysis of Fuel Temperature Variations in the MCNP Model of the Annular Core Research Reactor	3
Commentary	3
High-Accuracy Pulse Shape Discrimination for LSO/LuYAP Crystals Using a CNN-BiLSTM Deep Learning Model	3
Analysis of AP1000 Small-Break Loss-of-Coolant Accident Using Reactor Transient Simulator	3
Investigation of High-Temperature Compatibility of Select Oxides with Yttrium Hydride for Micro and Space Reactor Applications	3
Design and Demonstration of an Additively Manufactured Integrated Pressure Limiting Structure for Insertion into a Nuclear Research Reactor	3
Correlation Method of 3-D Detection of Distant Sources of Gamma Radiation and Neutrinos by Intensity Interferometry	3
Effects of Compatibilizers on the Rheological, Thermal, Mechanical, and γ-Ray Shielding Properties of WO 3 /PP Composites	3
Scientific and Cultural Heritage in Argentina’s Nuclear Sector: Meanings and Dynamics of Activation at the Bariloche Atomic Center	2
TRACE Assessment for Simulating Density Wave Oscillations in a Full-Scale BWR Rod Bundle Under Natural Circulation	2
Stability Tests and Analysis of a Low-Pressure Natural Circulation Loop with Flashing Instability	2
Experimental and Numerical Reassessment of Real-World Defects in Nuclear Components Through Additively Manufactured Physical Twins	2
Detecting Anomalies in Simulated Nuclear Data Using Autoencoders	2
Constitutive Modeling of Anisotropic Plasticity with ML Algorithms in Metals	2
High-Fidelity Modeling and Experiments to Inform Safety Analysis Codes for Heat Pipe Microreactors	2
SAM: A Modern System Code for Advanced Non-LWR Safety Analysis	2
Integrating Econometrics and Artificial Intelligence to Assess the Impact of Trade on Nuclear Proliferation	2
Toward a Better Understanding of Reflood Thermal Hydraulics: A Summary of the OECD/NEA RBHT Project	2
Convolutional Neural Network–Aided Temperature Field Reconstruction: An Innovative Method for Advanced Reactor Monitoring	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
A Risk Approach to the Management for the Pre-Defueled Phase in the Decommissioning Transition Stage	2
Resilience Governance in Nuclear Safety: Insights from China’s AI-Driven Innovative Practices	2
Analysis of Sustainable and Carbon-Free Nuclear Power for Enhancing Data Center Energy Security in the Artificial Intelligence Era	2
Lumped Parameter Analysis of Autogenous Propellant Pressurization System for Nuclear Thermal Rocket	2
Formation of Organic Tellurides and Organic Iodides Together Under Gamma Radiation	2
A Fan-Controlled Sodium-to-Air Heat Exchanger Configuration for Failsafe Decay Heat Removal in Sodium-Cooled Fast Reactors	2
Direct Numerical Simulation of Single- and Two-Phase Flows for Nuclear Engineering Geometries	2
Research Activities Associated with the Treatment of Potential Common-Cause Failures in Event and Condition Assessments	2
Evaluation of Alternative Safety Cooling Systems for Open Pool Research Reactor with Downward Flow	2
Thermal Assessment of Repository Footprint Requirement for Advanced Fuel Cycles	2
Enhanced Boiling Heat Transfer and Critical Heat Flux Characteristics of Fe 3 O 4 Nanofluid Under	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
Inferential-Statistical Reevaluation of Spent Fuel Zircaloy Cladding Integrity	2
Simplified Reactor Model for Microreactor Coupled with Helium Closed Brayton Cycle	2
Bayesian Calibration of UO 2 Creep Rates as a Tool for Accelerated Fuel Qualification	2
Preventing Reverse Engineering of Critical Industrial Data with DIOD	2
Multiphysics Analysis of PLOFC and DLOFC Accidents in the HTGR-TR	2
Influence of Iodine Chemistry in I 2 Scrubbing Modeling	2
Benchmarking Neutron Counting System for Passive Measurements and Active Interrogation of Unknown Objects for Fissile and Fissionable Materials Determination	2
Computational Framework for Estimating Cost of Equipment Disposal for Advanced Reactors	2
Localization of Stationary and Moving Radiation Sources Using a Feedforward Neural Network with an Array of Sensors	2
Adaptive Sampling Limit Surface Search Application to Identify Cliff-Edge Effects in Severe Accident Uncertainty Analysis	2
Prediction of Flooding Characteristic in Pulsed Disc and Doughnut Extraction Column Using LASSO Method	2
Evaluation of the New ENDF/B-VIII.0 Nuclear Data Library on Neutronic Parameters Calculations for First Core RSG-GAS Reactor	2
Evaluation of Neutron Scattering and Shielding Behavior in Epoxy-hBN Composites for Nuclear Applications	2
Technoeconomic Design Optimization for Fast Reactors. Part I: Workflow Development and Case Study for Small LFR District Energy Application	2
Exploring the Feasibility of Kuiper Belt Missions Supported by Centrifugal Nuclear Thermal Propulsion	2
Technical Reviewers	2
Digitalization, Management, and Synthesis of Thermal-Hydraulic Legacy Data Using the Dynamical System Scaling	2
Comments on the Physics of the Frisch-Peierls Memorandum	2
Versatile Testing Facility for Heavy Liquid Metal–Cooled Fast Reactor at the University of Pittsburgh	2
Pulse Shape Discrimination of Neutrons and Gamma Rays Using Neuromorphic Models	2
Role of Accelerated Burnup Irradiation Testing in Support of Accelerated Fuel Qualification	2
ENTS: A Novel Algorithm for Sampling-Based Dynamic Probabilistic Risk Assessment	2
Numerical Analysis of Heat Pipe Performance Considering Helium Gap Effects	2
Probabilistic Fracture Analysis for a Boiling Water Reactor Pressure Vessel During Transition to Decommissioning	2
Radioisotopes for Nuclear Medicine: An Overview	2
A Batch Refueling Framework for Implementing the Sourdough Fuel Cycle and Waste Management Strategy in the EIRENE Novel Molten Salt Reactor Design	2
Glove Operation Compartment with Cuboid Cans for Efficient Handling of Size-Reduced Solid Waste Generated from Plutonium-Contaminated Glovebox Dismantling Activities	2
Novel Approach for Network Data Exchange Among Safety-Related Control Systems of Nuclear Reactors	2
Techniques for Sensitivity Analysis in Severe Accidents: A Comparative Study	2
Analytical Model of Natural Circulation with a Sinusoidal Heat Input in a PWR	2
Thermal-Hydraulic Behavior and Safety Characteristics of the NHR200-II Reactor During Small-Break Loss-of-Coolant Accidents	2
A MOOSE-Based Model for Fission Product Transport and Source Term Estimation for High-Temperature Gas-Cooled Reactors	2
Release Behavior of Gaseous Ruthenium Tetroxide During Heating of High-Level Liquid Waste Simulant During Simulated Accident Conditions	2
Thorium and Uranium, Specific Surfaces, and Minerals in Bentonites	2
Experimental Investigation of Erosion and Corrosion of Aluminized and Non-Aluminized Steels Under High-Velocity Lead Flow	2
Refueling Considerations for 99 Mo Production in a CANDU Reactor	2
Optimized FSF Controller for Bulk Power Control of Large-Core PHWRs	2
Experimental Model to Study Characteristics of Radon Cover in Waste Landfills	2
Development of an Extended State Observer for Monitoring of a PWR Based on a Two-Point Kinetic Model	2
Explainable, Deep Reinforcement Learning–Based Decision Making for Operations and Maintenance	2
Comparative Consequence Analysis for a Heat Pipe–Cooled, TRISO-Fueled Microreactor Operating Across Distinct Climates	2
Simulation and Mitigation of False Data Injection Cyberattacks on a Space Nuclear Reactor Power System	2
Fiberoptic Laser-Induced Breakdown Spectroscopy System for in situ Measurement in a Hazardous Environment	2