OOIR: Observatory of International Research

Papers

(The median citation count of Nuclear Technology is 1. The table below lists those papers that are above that threshold based on CrossRef citation counts [max. 250 papers]. The publications cover those that have been published in the past four years, i.e., from 2020-04-01 to 2024-04-01.)

Article	Citations
BISON: A Flexible Code for Advanced Simulation of the Performance of Multiple Nuclear Fuel Forms	76
Kilopower Project: The KRUSTY Fission Power Experiment and Potential Missions	60
KRUSTY Reactor Design	59
Main Findings, Remaining Uncertainties and Lessons Learned from the OECD/NEA BSAF Project	39
Results of the KRUSTY Nuclear System Test	36
Pronghorn: A Multidimensional Coarse-Mesh Application for Advanced Reactor Thermal Hydraulics	30
Coupled Multiphysics Simulations of Heat Pipe Microreactors Using DireWolf	30
Rattlesnake: A MOOSE-Based Multiphysics Multischeme Radiation Transport Application	30
Heat Transport and Power Conversion of the Kilopower Reactor Test	26
Automatic Differentiation in MetaPhysicL and Its Applications in MOOSE	22
Toward Exascale: Overview of Large Eddy Simulations and Direct Numerical Simulations of Nuclear Reactor Flows with the Spectral Element Method in Nek5000	21
Kilowatt Reactor Using Stirling TechnologY (KRUSTY) Component-Critical Experiments	18
Continuous Integration, In-Code Documentation, and Automation for Nuclear Quality Assurance Conformance	17
KRUSTY Experiment: Reactivity Insertion Accident Analysis	15
Sockeye: A One-Dimensional, Two-Phase, Compressible Flow Heat Pipe Application	15
Results of the KRUSTY Warm Critical Experiments	15
Kilowatt Reactor Using Stirling TechnologY (KRUSTY) Cold Critical Measurements	14
Method of Characteristics for 3D, Full-Core Neutron Transport on Unstructured Mesh	14
Market Basis for Salt-Cooled Reactors: Dispatchable Heat, Hydrogen, and Electricity with Assured Peak Power Capacity	14
Cardinal: A Lower-Length-Scale Multiphysics Simulator for Pebble-Bed Reactors	13
On the Origins of Lagrangian Hydrodynamic Methods	12
Space Nuclear Propulsion Fuel and Moderator Development Plan Conceptual Testing Reference Design	12
Redox Behavior of Moisture in LiCl-KCl Eutectic Melts: A Cyclic Voltammetry Study	11
The MOOSE Multiphysics Computational Framework for Nuclear Power Applications: A Special Issue of Nuclear Technology	11
Development of the NuScale Power Module in the INL Modelica Ecosystem	11

Weapons Radiochemistry: Trinity and Beyond	10
The Carbon Value of Nuclear Power Plant Lifetime Extensions in the United States	10
Nuclear Science for the Manhattan Project and Comparison to Today’s ENDF Data	10
Radiation Source Localization Using Surrogate Models Constructed from 3-D Monte Carlo Transport Physics Simulations	9
Initial Exploratory Reactor Physics Assessment of Nonconventional Fuel Concepts for Very Compact Small Modular Reactors Using Hydroxides as Coolants and/or Moderators	9
Convective and Radiative Heat Transfer in Molten Salts	9
Prospects for Nuclear Microreactors: A Review of the Technology, Economics, and Regulatory Considerations	9
Structural Ignorance of Expertise in Nuclear Safety Controversies: Case Analysis of Post-Fukushima Japan	9
Challenges in Containment Thermal Hydraulics	9
Modeling of the Molten Salt Reactor Experiment with SCALE	9
Separating Nuclear Reactors from the Power Block with Heat Storage to Improve Economics with Dispatchable Heat and Electricity	8
Grizzly and BlackBear: Structural Component Aging Simulation Codes	8
P2M Simulation Exercise on Past Fuel Melting Irradiation Experiments	8
Production of High-Purity^52gMn from^natV Targets with Alpha Beams at Cyclotrons	8
A Concept Study on Advanced Radioisotope Solid Solutions and Mixed-Oxide Fuel Forms for Future Space Nuclear Power Systems	7
A New Yield Assessment for the Trinity Nuclear Test, 75 Years Later	7
MASTODON: An Open-Source Software for Seismic Analysis and Risk Assessment of Critical Infrastructure	7
Trinity by the Numbers: The Computing Effort that Made Trinity Possible	7
Application of Artificial Intelligence in Detection and Mitigation of Human Factor Errors in Nuclear Power Plants: A Review	7
Mutual Integration of Classical and Dynamic PRA	7
Multi-Index Measurement of Fatigue Degree Under the Simulated Monitoring Task of a Nuclear Power Plant	7
A Fuzzy CREAM Method for Human Reliability Analysis in Digital Main Control Room of Nuclear Power Plants	7
The Taming of Plutonium: Plutonium Metallurgy and the Manhattan Project	7
Comparison Between Historic Nuclear Explosion Yield Formulas	7
Nuclear Reactor Transient Diagnostics Using Classification and AutoML	7
Dynamic PRA Methods to Evaluate the Impact on Accident Progression of Accident Tolerant Fuels	7
Multiscale Simulations of Thermal Transport in W-UO₂ CERMET Fuel for Nuclear Thermal Propulsion	7
Criticality Experiments with Fast ²³⁵U and ²³⁹Pu Metal and Hydride Systems During the Manhattan Project	7
Electrochemical and Laser-Induced Breakdown Spectroscopy Signal Fusion for Detection of UCl₃-GdCl₃-MgCl₂ in LiCl-KCl Molten Salt	6
Nuclear Air-Brayton Power Cycles with Thermodynamic Topping Cycles, Assured Peaking Capacity, and Heat Storage for Variable Electricity and Heat	6
Plutonium-238 Production Program Results, Implications, and Projections from Irradiation and Examination of Initial NpO₂ Test Targets for Improved Production	6
Mankala Chronicles: Nuclear Energy Financing and Cooperative Corporate Form in Finland	6
A Worker’s Fitness-for-Duty Status Identification Based on Biosignals to Reduce Human Error in Nuclear Power Plants	6
Heat Transfer Enhancement Using Different SiO₂ Nanofluid Mixing Conditions on a Downward-Facing Heating Surface	6
Turbulent Mixing Models and Other Mixing Coefficients in Subchannel Codes—A Review Part A: Single Phase	6
Bayesian Network–Based Fault Diagnostic System for Nuclear Power Plant Assets	6
Presentation of the xM3 Test Case of the P2M Simulation Exercise and Modeling with the Fuel Performance Code ALCYONE	6
Comparison of Two Different Sized Small-Break LOCAs on the Passive Safety Injection Line Using SMART-ITL Data	6
Electroencephalography-Based Intention Monitoring to Support Nuclear Operators’ Communications for Safety-Relevant Tasks	6
Steady-State and Transient Benchmarks of GOTHIC to the Molten Salt Reactor Experiment	6
Scalable Feature Tracking for Finite Element Meshes Demonstrated with a Novel Phase-Field Grain Subdivision Model	6
Experimental Characterization of Leak Detection Systems in HLM Pool Using LIFUS5/Mod3 Facility	6
Who Invented the Trinity Nuclear Test’s Christy Gadget? Patents and Evidence from the Archives	6
A Stylized 3-D Benchmark Problem Set Based on the Pin-Fueled SmAHTR	6
Phenomenon Identification and Ranking Table Development for Future Application Figure-of-Merit Studies on Thermal Energy Storage Integrations with Light Water Reactors	6
Steady-State Thermal-Hydraulic Model for Fluoride-Salt-Cooled Small Modular High-Temperature Reactors	6
The Power and Limits of Classification: Radioactive Waste Categories as Reshaped by Disposal Options	6
Development of Subchannel Void Sensor for Wide Pressure and Temperature Ranges and Its Application to Boiling Flow Dynamics in a Heated Rod Bundle	5
Research on the Preliminary Prediction of Nuclear Core Design Based on Machine Learning	5
The Los Alamos Computing Facility During the Manhattan Project	5

Identification of Carbon in Glassy Cesium-Bearing Microparticles Using Electron Microscopy and Formation Mechanisms of the Microparticles	5
Hybrid System Level and Coarse Grid CFD Tool for Three-Dimensional Natural Circulation, Mixing, and Stratification Modeling	5
Advancements in Yttrium Hydride Moderator Development	5
It’s About Time: Jet Interactions in an Asymmetrical Plenum	5
Reactor Physics Assessment of Potential Feasibility of Using Advanced, Nonconventional Fuels in a Pressure Tube Heavy Water Reactor to Destroy Americium and Curium	5
Foundations for a Fission Battery Digital Twin	5
Dynamic PRA-Based Estimation of PWR Coping Time Using a Surrogate Model for Accident Tolerant Fuel	5
Critical Assemblies: Dragon Burst Assembly and Solution Assemblies	5
Fabrication of UN-Mo CERMET Nuclear Fuel Using Advanced Manufacturing Techniques	5
NEA Framing Nuclear Megaproject “Pathologies”: Vices of the Modern Western Society?	5
Pressure Drop Correlation Improvement for the Near-Wall Region of Pebble-Bed Reactors	5
Quantitative Evaluation on the Effect of Experience Under Emergency Situations in NPP Main Control Room Based on Multimodal Data	5
Assessment of Screen-Covered Grooved Sodium Heat Pipes for Microreactor Applications	4
Modeling Tritium Retention in Graphite for Fluoride-Salt-Cooled High-Temperature Reactors	4
Transmission of Images on High-Temperature Nuclear-Grade Metallic Pipe with Ultrasonic Elastic Waves	4
Airborne Release Fractions from Surrogate Nuclear Waste Fires Containing Lanthanide Nitrates and Depleted Uranium Nitrate in 30% Tributyl Phosphate in Kerosene	4
Tellurium Behavior in the Containment Sump: Dissolution, Redox, and Radiolysis Effects	4
Enhanced Bentonite/PVA Matrix for Advanced Shielding Applications	4
Numerical Simulation and Validation of Debris Bed Self-Leveling Behavior with Mixed-Density Particles Using CFD-DEM Coupling Algorithm	4
Severe Accident Phenomena: A Comparison Among the NuScale SMR, Other Advanced LWR Designs, and Operating LWRs	4
Investigating the Heat Transfer Characteristics of Impinging Flow on a Downward-Facing Surface	4
Sensitivity of SC-HTGR Conduction Cooldown to Reactor Cavity Cooling System Failure	4
Acoustic Analysis of the Effects of Vapor-Liquid Interfacial Morphology on Pool-Boiling Heat Transfer	4
Assessment of Radiation Background Suppression Using Phoswich Detectors for In Vivo Pb-210 Measurements: A Simulation Study	4
Development of an Integrated Computer Code System for Analyzing Irradiation Behaviors of a Fast Reactor Fuel	4
Parametric Analysis of an Optical Fiber–Based Gamma Thermometer for University Research Reactors Using an Analytic Thermal Model	4
A New Method to Efficiently Estimate the Equilibrium State of Pebble Bed Reactors	4
Neutronics Calculation Advances at Los Alamos: Manhattan Project to Monte Carlo	4
Application of Cable Condition Monitoring Technologies to Assess Age-Related Degradation of Industrial Cables Installed in Harsh Environments	4
SCALE 6.2.4 Validation for Light Water Reactor Decay Heat Analysis	4
Novel Deep Space Nuclear Electric Propulsion Spacecraft	4
Radioactive Aerosol Control and Decontamination in the Decommissioning of the Fukushima Daiichi Nuclear Power Station	4
Deliquescence of Eutectic LiCl-KCl Diluted with NaCl for Interim Waste Salt Storage	4
Integrating Advanced Modeling and Accelerated Testing for a Modernized Fuel Qualification Paradigm	4
State-of-the-Art Reactor Consequence Analyses Project: Uncertainty Analyses for Station Blackout Scenarios	4
Predictive Modeling of a Simple Field Matrix Diffusion Experiment Addressing Radionuclide Transport in Fractured Rock. Is It So Straightforward?	4
Pattern Recognition–Based Technique for Control Rod Position Identification in Pressurized Water Reactors	4
Validation of Pronghorn Pressure Drop Correlations Against Pebble Bed Experiments	4
The UO ₂ Power-to-Melt Experiment Performed in the High Burnup Chemistry International Program	4
Estimation of Waste Package Inventories and Characteristics from Different Advanced Fuel Cycles	4
Temperature and Power Specific Mass Scaling for Commercial Closed-Cycle Brayton Systems in Space Surface Power and Nuclear Electric Propulsion Applications	4
Formation and Chemical Transformations of Steel Corrosion Products in the Primary Systems of Nuclear Power Plants	3
Effective Thermal Conductivity of Typical Composite Plate with Inner Heat Source and Temperature Difference	3
Space Nuclear Power and Propulsion at USNC-Tech	3
Review of Candidate Techniques for Material Accountancy Measurements in Electrochemical Separations Facilities	3
Numerical Investigation and Parametric Study on Thermal-Hydraulic Characteristics of Particle Bed Reactors for Nuclear Thermal Propulsion	3
Steady-State In-Pile Nuclear Thermal Propulsion Experimental Testbed Initial Demonstration at The Ohio State University Research Reactor	3
Coupling Gothic and RELAP5 for Passive Containment Cooling Modeling	3
Considerations for Hydride Moderator Readiness in Microreactors	3
Issues of Safety Assessment of New Russian NPP Projects in View of Current Requirements for the Probability of a Large Release	3
Evaluation of Fixed Absorber Reactivity Measurement in the Prototype Fast Reactor Monju	3
Enhancing the One-Dimensional SFR Thermal Stratification Model via Advanced Inverse Uncertainty Quantification Methods	3
Direct Numerical Simulation and Large Eddy Simulation of a 67–Pebble Bed Experiment	3
Lower-Weight Landmine Detection Under Various Buried Conditions Based on PGNAA and Machine Learning	3
Cross-Section Calculations for the Production of ¹²³I and ¹²⁴I Radioisotopes via (p,n) and (p,2n) Reactions Using Collective Nuclear Level Density Model	3
A Redundancy-Guided Approach for the Hazard Analysis of Digital Instrumentation and Control Systems in Advanced Nuclear Power Plants	3
Development of an Epoxy Solidification Method for Radioactive Spent Resins	3
Rudolf Peierls’s “Outline of the Development of the British Tube Alloy Project”: A 1945 Account of the Earliest UK Work on Atomic Energy	3
A Versatile Remediation Module for Remote Repair of Spent Nuclear Fuel and High-Level Waste Storage Containers	3
Fabrication and Characterization of Zirconium Silicide for Application to Gas-Cooled Fast Reactors	3
Denoising Algorithm for Subtle Anomaly Detection	3
A Global Model for Predicting Vacuum Drying of Used Nuclear Fuel Assemblies	3
Simulation of the Fast Reactor Fuel Assembly Duct-Bowing Reactivity Effect Using Monte Carlo Neutron Transport and Finite Element Analysis	3
X-Ray and Neutron Radiography System Optimization by Means of a Multiobjective Approach and a Simplified Ray-Tracing Method	3
ASTRID, Back to the Future: Bridging Scales in the Development of Nuclear Infrastructures	3
Making Construction Cost Estimate of Nuclear Power Plants Credible: Assessing Impact of Unknown Unknowns	3
Recent ²³⁸Pu Production Activities at Idaho National Laboratory	3
Equation of State: Manhattan Project Developments and Beyond	3
Reactor Physics Analysis Assessment of Feasibility of Using Advanced, Nonconventional Fuels in a Pressure Tube Heavy Water Reactor to Destroy Long-Lived Fission Products	3
Machine Learning Surrogates of a Fuel Matrix Degradation Process Model for Performance Assessment of a Nuclear Waste Repository	3
Global Sensitivity Analysis and Bayesian Calibration on a Series of Reflood Experiments with Varying Boundary Conditions	3
On the Symmetry of Blast Waves	3
Experimental Method for Verification of Calculated ¹³⁷Cs Content in Nuclear Fuel Assemblies	2
Development of an Experimentally Validated MCNP6 Model for ¹¹C Production via the ¹⁴N(p,α) Reaction Using a GE PETtrace Cyclotron	2
Breaking Out of a Niche: Lessons for SMRs from Sustainability Transitions Studies	2
Treatment of Simulated Radioactive Wastewater Using Reverse Osmosis and Membrane Distillation	2
Condition Assessment of Nuclear Power Plant Equipment Based on Machine Learning Methods: A Review	2
Evaluation of Fuel Reactivity Worth Measurement in the Prototype Fast Reactor Monju	2
Review of Passive Heat Removal Strategies for Nuclear Microreactor Systems	2
Toward an In-Depth Material Model for Cermet Nuclear Thermal Rocket Fuel Elements	2

Extension of a Level 2 PSA Event Tree Based on Results of a Probabilistic Dynamic Safety Analysis of Induced Steam Generator Tube Rupture	2
Radiation Compatibility of Geopolymer, Polymer, and Composite Materials for Use as Inner Shielding in Radioactive Waste Containers—A Simulation-Based Study	2
Direct Dissolution of Used Nuclear Fuel in PUREX Solvent: Review and Flowsheet Development	2
Release Behaviors of Elements from an Ag-In-Cd Control Rod Alloy at Temperatures up to 1673 K	2
The Trinity High-Explosive Implosion System: The Foundation for Precision Explosive Applications	2
Microstructural and Mechanical Properties of Nitrogen Ion Irradiated 316 Stainless Steel	2
The Manhattan Project Nuclear Science and Technology Developments at Los Alamos: A Special Issue of Nuclear Technology	2
Hydrogen Generation from α Radiolysis of Organic Materials in Transuranic Waste. Comparison Between Experimental Data and STORAGE Calculations	2
Preliminary Results for In-Situ Alternative Propellants for Nuclear Thermal Propulsion	2
Development of Emergency Information System to Support Nuclear Power Plant Management in Severe Accident	2
Gamma and Decay Energy Spectroscopy Measurements of Trinitite	2
Partial Cross-Section Calculations for PGNAA Based on a Deterministic Neutron Transport Solver	2
TRACE Analysis of a Loss of Alternating-Current Power Without Rod Insertion for the NuScale Power Module—I: Basic Event Progression and Long-Term Behavior	2
Operational Considerations for Space Fission Power and Propulsion Platforms	2
Validation Matrix for Pool Scrubbing Models	2
Testing of an Element Tracer Dilution Method for Measurement of Total Mass of Molten Salt in a Nuclear Fuel Cycle Process or Molten Salt Reactor	2
Organic Telluride Formation from Paint Solvents Under Gamma Irradiation	2
Finely Divided Metal as Nuclear Reactor Fuel	2
Reevaluating the Current U.S. Nuclear Regulatory Commission’s Safety Goals	2
Use of Risk Insights in the Practical Implementation of an Integrated Risk-Informed Decision-Making Framework	2
Research on the Performance of Nuclear Battery with SiC-Schottky and GaN-PIN Structure	2
A Radiation-Tolerant Wireless Communication System for Severe Accident Monitoring Without Relying on Rad-Hardened Electronic Components	2
Sensitivity Studies to Assess the Impact of Geometry and Operating/Boundary Condition Perturbations on Thermal-Hydraulic Behavior of Advanced Fuel Channels in Pressure Tube Heavy Water Reactors with U	2
Changing the System Culture: Mobilizing the Social Sciences in the Swedish Nuclear Waste System	2
Experimental Studies on Two-Layer Corium Heat Transfer in Light Water Reactor Lower Head in LIVE2D Facility	2
Woolwich, Bruceton, Los Alamos: Munroe Jets and the Trinity Gadget	2
The PyNE-Based Burnup Analysis Method for Accelerator-Driven Subcritical Systems	2
Water Migration and Swelling in Engineered Barrier Materials for Radioactive Waste Disposal	2
From “Inherently Safe” to “Proliferation Resistant”: New Perspectives on Reactor Designs	2
Benchmark of the Kilowatt Reactor Using Stirling TechnologY (KRUSTY) Component Critical Configurations	2
An Integrated Risk Assessment Process of Safety-Related Digital I&C Systems in Nuclear Power Plants	2
Comparison of Irradiated TRISO Fuel Radioactivity from Multiple Advanced Reactor Designs	2
Void Fraction and Interfacial Friction in Vertical Circular Pipes with the Square Top End Under Flooding Conditions	2
Toward an Agent-Based Blackboard System for Reactor Design Optimization	2
Radionuclide Transport in Channel Networks with Radial Diffusion in the Porous Rock Matrix	2
Corrosion Behavior of Pre-Carburized Hastelloy N, Haynes 244, Haynes 230, and Incoloy 800H in Molten FLiNaK	2
Fermi at Trinity	2
Improving Pulse Shape Discrimination in Organic Scintillation Detectors by Understanding Underlying Data Structure	2
A CNN-LSTM–Based Model to Fault Diagnosis for CPR1000	2
Covert Cognizance: A Novel Predictive Modeling Paradigm	2
Steady-State Subchannel Thermal-Hydraulic Assessment of Advanced Uranium-Based and Thorium-Based Fuel Bundle Concepts for Potential Use in Pressure Tube Heavy Water Reactors	2
Feasibility Assessment of a Natural-Circulation Salt Irradiation Loop in the Advanced Test Reactor	2
Experiment Validation Protocol for Flux Wire Measurements in the Advanced Test Reactor	2
Design and Analysis of an Internal Remote Monitoring System for Spent Nuclear Fuel Stored in a Dry Cask	2
STORAGE: A Source Term Model for Intermediate-Level Radioactive Waste	2
Predictive and Inverse Modeling of a Radionuclide Diffusion Experiment in Crystalline Rock at ONKALO (Finland)	2
Canadian Contributions to the Manhattan Project and Early Nuclear Research	2
Multiaxial Plastic Deformation of Zircaloy-4 Nuclear Fuel Cladding Tubes	2
An Exploration of Mission Concepts That Could Utilize Small RPS	2
Transitioning to a Sustainable Thorium Fuel Cycle in Pressurized Water Reactors Using Bimetallic Thorium-Zirconium Alloy Cladding	2
Uncertainty Quantification of the 1-D SFR Thermal Stratification Model via the Latin Hypercube Sampling Monte Carlo Method	2
Multi-Mission Thermoelectric Generator Fueling Testing and Integration Operations for Mars 2020	2
TRACE Analysis of a Loss of Alternating-Current Power Without Rod Insertion for the NuScale Power Module—II: Sensitivity to Varying Initial Temperature	2
The Origins of Blast-Loaded Vessels	1
Modeling of an Energy-Diverse Embedded Grid for Microreactor Integration	1
Reliability Evaluation of Complex Nuclear Energy Redundancy Systems with Atypical Time-Distribution Events	1
“Economizing” TEPCO’s Responsibility for the Fukushima Daiichi Nuclear Power Plant Accident	1
Newly Developed Method for Liquid Thin Film Thickness Measurement Using Optical Fiber–Based Reflective Probe	1
Risk, “Radiophobia,” and Social Learning: Applying Lessons from the Literature	1
Nonnuclear Experimental Capabilities to Support Design, Development, and Demonstration of Microreactors	1
Transition Core Analysis for HEU to LEU Fuel Conversion at the University of Missouri Research Reactor	1
An Experimental and Theoretical Examination of Air Ingress Rates During Small- and Medium-Break Air Ingress Accidents	1
Experimental Analysis of Steam Generator Tube Rupture in CIRCE Facility for MYRRHA Configuration	1
Thermal-Hydraulic and Engineering Evaluations of New LOCA Testing Methods in TREAT	1
Emissivity of Grade 91 Ferritic Steel: Additional Measurements on Role of Surface Conditions and Oxidation	1
Recovery of Zirconium from Zircaloys Using a Hydrochlorination Process	1
Benchmark Simulation of the Natural Convection Shutdown Heat Removal Test Facility Using SAM	1
Measurement of Local Void Fraction of Air-Water Flow in an 8 × 8 Rod Bundle Using High-Resolution Gamma-Ray Tomography	1
Neutronic Performance Analysis of Inner-Side Chromium Coatings for Accident Tolerant Fuel	1
Integral Effect Test and MARS-KS Calculation with Uncertainty Propagation Analysis for Direct Vessel Injection Line Break Intermediate-Break Loss-of-Coolant Accident	1
PHWR Reactivity Device Incremental Macroscopic Cross Sections and Reactivities for a Molybdenum-Producing Bundle and a Standard Bundle	1
Nuclear Power Concepts and Development Strategies for High-Power Electric Propulsion Missions to Mars	1
Preliminary Modeling of Chloride Deposition on Spent Nuclear Fuel Canisters in Dry Storage Relevant to Stress Corrosion Cracking	1
Separation of Flux/Dose Contributions from Multiple Transport Pathways in Monte Carlo Shielding Analyses of a Consolidated Interim Spent Nuclear Fuel Storage Facility	1
Advanced Reactor Control and Operations (ARCO): A University Research Facility for Developing Optimized Digital Control Rooms	1
Experimental Measurement and Multiphysics Simulation of Tritium Transport in Neutron-Irradiated Flibe Salt	1
Numerical Simulation of Wall Condensation from a Superheated Steam and Air Mixture in a Vertical Pipe	1
Overview and Recommendations for Cyber Risk Assessment in Nuclear Power Plants	1
Enhancement of Fast Neutron Detection in Liquid Scintillator Detectors	1
Transient System Thermal-Hydraulic Assessment of Advanced Uranium- and Thorium-Based Fuel Bundle Concepts for Potential Use in Pressure Tube Heavy Water Reactors—II: Full-Core Analyses	1
An Optimized Method for Bonner Sphere Spectrometer Design and Validation by Measuring ²⁵²Cf Spectra	1
Enhanced Lasso Regularization-Based Self-Adaptive Feature Selection Algorithm for the High-Dimensional Uncertainty Quantification of TREAT Transient Test Modeling	1
Foreword: Special issue on the U.S. Department of Energy Microreactor Program	1
An Assessment of Deep Borehole Disposal Post-Closure Safety	1
Revisiting Safety Culture: The Benefits of a New Cultural Analysis Framework for Safety Management	1
Molybdenum-99 from Molten Salt Reactor as a Source of Technetium-99m for Nuclear Medicine: Past, Current, and Future of Molybdenum-99	1
Reactor Performance and Safety Characteristics of Beryllium-Based Composite Moderators as Replacements for Graphite in mHTGRs	1
Explanation of Deep Learning–Based Radioisotope Identifier for Plastic Scintillation Detector	1
Multiphysics Analyses of the Bottom Components of the 3D Printed Transformational Challenge Reactor	1
In-Canal Assay of High Specific Activity ⁶⁰Co at the Advanced Test Reactor	1
Fuel Melting Simulation with FRAPCON/FRAPTRAN Codes for the Power-to-Melt-and-Maneuverability Simulation Exercise and Consideration of Model Modifications	1
Experimental Results of PbLi-Water Reaction Performed in LIFUS5/Mod3 Separate Effect Test Facility	1
Comparison of Analysis Results on Three Methods for Sampling Crud, a Radioactive Corrosion Product with Zinc-Injected Spent PWR Nuclear Fuel Rods	1
A Monte Carlo Study for Soft Tissue Equivalency of Potential Polymeric Biomaterials Used in Carbon Ion Radiation Therapy	1
Addressing Human and Organizational Factors in Nuclear Industry Modernization: A Sociotechnically Based Strategic Framework	1