OOIR: Observatory of International Research

Papers

(The TQCC of Nuclear Technology is 2. 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 2020-11-01 to 2024-11-01.)

Article	Citations
BISON: A Flexible Code for Advanced Simulation of the Performance of Multiple Nuclear Fuel Forms	95
Rattlesnake: A MOOSE-Based Multiphysics Multischeme Radiation Transport Application	41
Coupled Multiphysics Simulations of Heat Pipe Microreactors Using DireWolf	40
Pronghorn: A Multidimensional Coarse-Mesh Application for Advanced Reactor Thermal Hydraulics	38
Automatic Differentiation in MetaPhysicL and Its Applications in MOOSE	27
Prospects for Nuclear Microreactors: A Review of the Technology, Economics, and Regulatory Considerations	24
Sockeye: A One-Dimensional, Two-Phase, Compressible Flow Heat Pipe Application	23
Continuous Integration, In-Code Documentation, and Automation for Nuclear Quality Assurance Conformance	19
Nuclear Science for the Manhattan Project and Comparison to Today’s ENDF Data	18
Method of Characteristics for 3D, Full-Core Neutron Transport on Unstructured Mesh	16
Space Nuclear Propulsion Fuel and Moderator Development Plan Conceptual Testing Reference Design	16
Cardinal: A Lower-Length-Scale Multiphysics Simulator for Pebble-Bed Reactors	16
On the Origins of Lagrangian Hydrodynamic Methods	14
The MOOSE Multiphysics Computational Framework for Nuclear Power Applications: A Special Issue of Nuclear Technology	13
Application of Artificial Intelligence in Detection and Mitigation of Human Factor Errors in Nuclear Power Plants: A Review	13
Modeling of the Molten Salt Reactor Experiment with SCALE	12
Structural Ignorance of Expertise in Nuclear Safety Controversies: Case Analysis of Post-Fukushima Japan	12
A Fuzzy CREAM Method for Human Reliability Analysis in Digital Main Control Room of Nuclear Power Plants	12
The Carbon Value of Nuclear Power Plant Lifetime Extensions in the United States	12
Initial Exploratory Reactor Physics Assessment of Nonconventional Fuel Concepts for Very Compact Small Modular Reactors Using Hydroxides as Coolants and/or Moderators	10
Comparison Between Historic Nuclear Explosion Yield Formulas	10
Weapons Radiochemistry: Trinity and Beyond	10
Heat Transfer Enhancement Using Different SiO₂ Nanofluid Mixing Conditions on a Downward-Facing Heating Surface	9
Presentation of the xM3 Test Case of the P2M Simulation Exercise and Modeling with the Fuel Performance Code ALCYONE	9
Advancements in Yttrium Hydride Moderator Development	9

Steady-State and Transient Benchmarks of GOTHIC to the Molten Salt Reactor Experiment	9
Plutonium-238 Production Program Results, Implications, and Projections from Irradiation and Examination of Initial NpO₂ Test Targets for Improved Production	9
Research on the Preliminary Prediction of Nuclear Core Design Based on Machine Learning	9
Grizzly and BlackBear: Structural Component Aging Simulation Codes	9
Separating Nuclear Reactors from the Power Block with Heat Storage to Improve Economics with Dispatchable Heat and Electricity	9
A Concept Study on Advanced Radioisotope Solid Solutions and Mixed-Oxide Fuel Forms for Future Space Nuclear Power Systems	8
Pressure Drop Correlation Improvement for the Near-Wall Region of Pebble-Bed Reactors	8
Production of High-Purity^52gMn from^natV Targets with Alpha Beams at Cyclotrons	8
P2M Simulation Exercise on Past Fuel Melting Irradiation Experiments	8
The Taming of Plutonium: Plutonium Metallurgy and the Manhattan Project	8
Criticality Experiments with Fast ²³⁵U and ²³⁹Pu Metal and Hydride Systems During the Manhattan Project	8
Electroencephalography-Based Intention Monitoring to Support Nuclear Operators’ Communications for Safety-Relevant Tasks	8
Bayesian Network–Based Fault Diagnostic System for Nuclear Power Plant Assets	8
Considerations for Hydride Moderator Readiness in Microreactors	7
Scalable Feature Tracking for Finite Element Meshes Demonstrated with a Novel Phase-Field Grain Subdivision Model	7
Multi-Index Measurement of Fatigue Degree Under the Simulated Monitoring Task of a Nuclear Power Plant	7
Nuclear Reactor Transient Diagnostics Using Classification and AutoML	7
Radioactive Aerosol Control and Decontamination in the Decommissioning of the Fukushima Daiichi Nuclear Power Station	7
Trinity by the Numbers: The Computing Effort that Made Trinity Possible	7
A New Yield Assessment for the Trinity Nuclear Test, 75 Years Later	7
Multiscale Simulations of Thermal Transport in W-UO₂ CERMET Fuel for Nuclear Thermal Propulsion	7
Integrating Advanced Modeling and Accelerated Testing for a Modernized Fuel Qualification Paradigm	7
Reactor Physics Assessment of Potential Feasibility of Using Advanced, Nonconventional Fuels in a Pressure Tube Heavy Water Reactor to Destroy Americium and Curium	6
A CNN-LSTM–Based Model to Fault Diagnosis for CPR1000	6
Mankala Chronicles: Nuclear Energy Financing and Cooperative Corporate Form in Finland	6
Enhanced Bentonite/PVA Matrix for Advanced Shielding Applications	6
Development of Subchannel Void Sensor for Wide Pressure and Temperature Ranges and Its Application to Boiling Flow Dynamics in a Heated Rod Bundle	6
It’s About Time: Jet Interactions in an Asymmetrical Plenum	6
Foundations for a Fission Battery Digital Twin	6
Predictive Modeling of a Simple Field Matrix Diffusion Experiment Addressing Radionuclide Transport in Fractured Rock. Is It So Straightforward?	6
Neutronics Calculation Advances at Los Alamos: Manhattan Project to Monte Carlo	6
The Power and Limits of Classification: Radioactive Waste Categories as Reshaped by Disposal Options	6
Investigating the Heat Transfer Characteristics of Impinging Flow on a Downward-Facing Surface	6
Who Invented the Trinity Nuclear Test’s Christy Gadget? Patents and Evidence from the Archives	6
Pattern Recognition–Based Technique for Control Rod Position Identification in Pressurized Water Reactors	6
Phenomenon Identification and Ranking Table Development for Future Application Figure-of-Merit Studies on Thermal Energy Storage Integrations with Light Water Reactors	6
SCALE 6.2.4 Validation for Light Water Reactor Decay Heat Analysis	6
Critical Assemblies: Dragon Burst Assembly and Solution Assemblies	5
The Los Alamos Computing Facility During the Manhattan Project	5
State-of-the-Art Reactor Consequence Analyses Project: Uncertainty Analyses for Station Blackout Scenarios	5
Equation of State: Manhattan Project Developments and Beyond	5
Denoising Algorithm for Subtle Anomaly Detection	5
NEA Framing Nuclear Megaproject “Pathologies”: Vices of the Modern Western Society?	5
The Nuclear, Humanities, and Social Science Nexus: Challenges and Opportunities for Speaking Across the Disciplinary Divides	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
Global Sensitivity Analysis and Bayesian Calibration on a Series of Reflood Experiments with Varying Boundary Conditions	5
Fabrication of UN-Mo CERMET Nuclear Fuel Using Advanced Manufacturing Techniques	5
Assessment of Screen-Covered Grooved Sodium Heat Pipes for Microreactor Applications	5
Application of Cable Condition Monitoring Technologies to Assess Age-Related Degradation of Industrial Cables Installed in Harsh Environments	5

Modeling Tritium Retention in Graphite for Fluoride-Salt-Cooled High-Temperature Reactors	4
ASTRID, Back to the Future: Bridging Scales in the Development of Nuclear Infrastructures	4
Fabrication and Characterization of Zirconium Silicide for Application to Gas-Cooled Fast Reactors	4
Explanation of Deep Learning–Based Radioisotope Identifier for Plastic Scintillation Detector	4
Estimation of Waste Package Inventories and Characteristics from Different Advanced Fuel Cycles	4
Validation of Pronghorn Pressure Drop Correlations Against Pebble Bed Experiments	4
Acoustic Analysis of the Effects of Vapor-Liquid Interfacial Morphology on Pool-Boiling Heat Transfer	4
Numerical Simulation and Validation of Debris Bed Self-Leveling Behavior with Mixed-Density Particles Using CFD-DEM Coupling Algorithm	4
Assessment of Radiation Background Suppression Using Phoswich Detectors for In Vivo Pb-210 Measurements: A Simulation Study	4
Parametric Analysis of an Optical Fiber–Based Gamma Thermometer for University Research Reactors Using an Analytic Thermal Model	4
Lower-Weight Landmine Detection Under Various Buried Conditions Based on PGNAA and Machine Learning	4
Evaluation of Fixed Absorber Reactivity Measurement in the Prototype Fast Reactor Monju	4
Development of an Integrated Computer Code System for Analyzing Irradiation Behaviors of a Fast Reactor Fuel	4
Novel Deep Space Nuclear Electric Propulsion Spacecraft	4
A New Method to Efficiently Estimate the Equilibrium State of Pebble Bed Reactors	4
Sensitivity of SC-HTGR Conduction Cooldown to Reactor Cavity Cooling System Failure	4
Development of an Epoxy Solidification Method for Radioactive Spent Resins	4
Radionuclide Transport in Channel Networks with Radial Diffusion in the Porous Rock Matrix	4
eBlock37 Microreactor Electrical Demonstration Unit	4
Cross-Section Calculations for the Production of ¹²³I and ¹²⁴I Radioisotopes via (p,n) and (p,2n) Reactions Using Collective Nuclear Level Density Model	4
Space Nuclear Power and Propulsion at USNC-Tech	4
Gamma and Decay Energy Spectroscopy Measurements of Trinitite	4
Nonnuclear Experimental Capabilities to Support Design, Development, and Demonstration of Microreactors	4
Nuclear Thermal-Hydraulic Phenomena: Bases and Challenges	4
Nuclear Power Concepts and Development Strategies for High-Power Electric Propulsion Missions to Mars	4
Deliquescence of Eutectic LiCl-KCl Diluted with NaCl for Interim Waste Salt Storage	4
Steady-State In-Pile Nuclear Thermal Propulsion Experimental Testbed Initial Demonstration at The Ohio State University Research Reactor	4
Review of Passive Heat Removal Strategies for Nuclear Microreactor Systems	4
Comprehensive Analysis and Evaluation of Fukushima Daiichi Nuclear Power Station Unit 3	4
The UO ₂ Power-to-Melt Experiment Performed in the High Burnup Chemistry International Program	3
STORAGE: A Source Term Model for Intermediate-Level Radioactive Waste	3
Hydrogen Generation from α Radiolysis of Organic Materials in Transuranic Waste. Comparison Between Experimental Data and STORAGE Calculations	3
Recent ²³⁸Pu Production Activities at Idaho National Laboratory	3
Experimental Method for Verification of Calculated ¹³⁷Cs Content in Nuclear Fuel Assemblies	3
Coupling Gothic and RELAP5 for Passive Containment Cooling Modeling	3
A Global Model for Predicting Vacuum Drying of Used Nuclear Fuel Assemblies	3
Comments on the Physics of the Frisch-Peierls Memorandum	3
Direct Numerical Simulation and Large Eddy Simulation of a 67-Pebble-Bed Experiment	3
Partial Cross-Section Calculations for PGNAA Based on a Deterministic Neutron Transport Solver	3
Changing the System Culture: Mobilizing the Social Sciences in the Swedish Nuclear Waste System	3
Convolutional Neural Network–Aided Temperature Field Reconstruction: An Innovative Method for Advanced Reactor Monitoring	3
Evaluation of Fuel Reactivity Worth Measurement in the Prototype Fast Reactor Monju	3
Benchmark of the Kilowatt Reactor Using Stirling TechnologY (KRUSTY) Component Critical Configurations	3
Water Migration and Swelling in Engineered Barrier Materials for Radioactive Waste Disposal	3
Design and Analysis of an Internal Remote Monitoring System for Spent Nuclear Fuel Stored in a Dry Cask	3
Machine Learning Surrogates of a Fuel Matrix Degradation Process Model for Performance Assessment of a Nuclear Waste Repository	3
Woolwich, Bruceton, Los Alamos: Munroe Jets and the Trinity Gadget	3
Predictive and Inverse Modeling of a Radionuclide Diffusion Experiment in Crystalline Rock at ONKALO (Finland)	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
Thermal Assessment of Repository Footprint Requirement for Advanced Fuel Cycles	3
Effective Thermal Conductivity of Typical Composite Plate with Inner Heat Source and Temperature Difference	3
Assessment of Factory Fabrication Considerations for Nuclear Microreactors	3
Breaking Out of a Niche: Lessons for SMRs from Sustainability Transitions Studies	3
Thermal-Hydraulic Research Supporting the Development of SMART	3
A Redundancy-Guided Approach for the Hazard Analysis of Digital Instrumentation and Control Systems in Advanced Nuclear Power Plants	3
Toward an In-Depth Material Model for Cermet Nuclear Thermal Rocket Fuel Elements	3
Coupled Computational Fluid Dynamics–Discrete Element Method Study of Bypass Flows in a Pebble Bed Reactor	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
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
Canadian Contributions to the Manhattan Project and Early Nuclear Research	3
On the Symmetry of Blast Waves	3
The Manhattan Project Nuclear Science and Technology Developments at Los Alamos: A Special Issue of Nuclear Technology	3
The Experimental and Simulation Results of LIVE-J2 Test—Investigation on Heat Transfer in a Solid–Liquid Mixture Pool	3
Radiation Compatibility of Geopolymer, Polymer, and Composite Materials for Use as Inner Shielding in Radioactive Waste Containers—A Simulation-Based Study	3
Formation and Chemical Transformations of Steel Corrosion Products in the Primary Systems of Nuclear Power Plants	3
Condition Assessment of Nuclear Power Plant Equipment Based on Machine Learning Methods: A Review	3
The Hypatia Experiment: Yttrium Hydride and Highly Enriched Uranium Critical Experiment	3
Trade-Offs Between Space Nuclear Systems Fueled with Highly Enriched Uranium and Low-Enriched Uranium	3
Resolution Analysis of Fast Neutron Imaging Based on D-T Neutron Source	3
Preliminary Modeling of Chloride Deposition on Spent Nuclear Fuel Canisters in Dry Storage Relevant to Stress Corrosion Cracking	3
A Monte Carlo Study for Soft Tissue Equivalency of Potential Polymeric Biomaterials Used in Carbon Ion Radiation Therapy	3
Uncertainty Quantification of the 1-D SFR Thermal Stratification Model via the Latin Hypercube Sampling Monte Carlo Method	3
Research on the Performance of Nuclear Battery with SiC-Schottky and GaN-PIN Structure	3
Preliminary Results for In-Situ Alternative Propellants for Nuclear Thermal Propulsion	2
From “Inherently Safe” to “Proliferation Resistant”: New Perspectives on Reactor Designs	2
Social Scientists in an Adversarial Environment: The Nuclear Regulatory Commission and Organizational Factors Research	2
PHWR Reactivity Device Incremental Macroscopic Cross Sections and Reactivities for a Molybdenum-Producing Bundle and a Standard Bundle	2
Direct Dissolution of Used Nuclear Fuel in PUREX Solvent: Review and Flowsheet Development	2
Toward an Agent-Based Blackboard System for Reactor Design Optimization	2
An Integrated Risk Assessment Process of Safety-Related Digital I&C Systems in Nuclear Power Plants	2

Operational Considerations for Space Fission Power and Propulsion Platforms	2
Experimental Analysis of Steam Generator Tube Rupture in CIRCE Facility for MYRRHA Configuration	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
Sensitivity Analysis of Transient Critical Heat Flux by RIA Under High-Pressure Flow Boiling Conditions in TRTL	2
Covert Cognizance: A Novel Predictive Modeling Paradigm	2
Experiment Validation Protocol for Flux Wire Measurements in the Advanced Test Reactor	2
Measurement of Local Void Fraction of Air-Water Flow in an 8 × 8 Rod Bundle Using High-Resolution Gamma-Ray Tomography	2
Validation Matrix for Pool Scrubbing Models	2
Adsorption of Radioactive Iodine Using Nanocarbon on ETS-10 as Adsorbent	2
Thermal-Hydraulic Transient Analyses for Primary Coolant System of HFRR Using RELAP5	2
Feasibility Assessment of a Natural-Circulation Salt Irradiation Loop in the Advanced Test Reactor	2
Discrete Element Method Simulation of the Idaho Calcine Simulant for Hot Isostatic Pressing Canister-Filling Process: Part 1	2
Evaluating the Improvement of Cross-Correlation–Based Flow Measurement by Periodic Fluid Injection	2
Experimental and Computational Verification of a New Remote Monitoring System Design for Spent Fuel Dry Cask Safeguards Using Small-Scale, Generic Diversion Scenarios	2
Transitioning to a Sustainable Thorium Fuel Cycle in Pressurized Water Reactors Using Bimetallic Thorium-Zirconium Alloy Cladding	2
High-Fidelity Modeling and Experiments to Inform Safety Analysis Codes for Heat Pipe Microreactors	2
Multi-Mission Thermoelectric Generator Fueling Testing and Integration Operations for Mars 2020	2
Void Fraction and Interfacial Friction in Vertical Circular Pipes with the Square Top End Under Flooding Conditions	2
Modeling of the P2M Past Fuel Melting Experiments with the FEMAXI-8 Code	2
Current Progress on the Development of the Integrated Waste Management Consent-Based Siting Process in the United States	2
Thirty Minutes Before the Dawn	2
Treatment of Simulated Radioactive Wastewater Using Reverse Osmosis and Membrane Distillation	2
A 100-Mrad (Si) JFET-Based Sensing and Communications System for Extreme Nuclear Instrumentation Environments	2
Finely Divided Metal as Nuclear Reactor Fuel	2
Adsorption Properties of Cs(I) and Co(II) on GMZ Bentonite Colloids	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
Modeling of an Energy-Diverse Embedded Grid for Microreactor Integration	2
Effects of Pipe Inclination on Global Two-Phase Flow Parameters	2
Numerical Simulations of Flow-Induced Deflections in MITR LEU Fuel Plate Due to Channel Size Disparity	2
Foreword: Special issue on the U.S. Department of Energy Microreactor Program	2
A Better Method to Calculate Fuel Burnup in Pebble Bed Reactors Using Machine Learning	2
The Trinity High-Explosive Implosion System: The Foundation for Precision Explosive Applications	2
A Framework to Assess Advanced Reactor Spent Fuel Management Facility Deployment	2
Multiaxial Plastic Deformation of Zircaloy-4 Nuclear Fuel Cladding Tubes	2
Automated Object Detection for Visual Inspection of Nuclear Reactor Cores	2
Westinghouse Test Facilities for Lead Fast Reactor Development	2
Assessing the Structure-Based Turbulence Model Performance for Thermal Striping Applications Using Symmetric Jet Experiments	2
Comparison of Irradiated TRISO Fuel Radioactivity from Multiple Advanced Reactor Designs	2
Evaluation of Control Rod Interaction Measurement in the Prototype Fast Reactor Monju	2
Development of Emergency Information System to Support Nuclear Power Plant Management in Severe Accident	2
Validation of Light Water Reactor Ex-Core Calculations with VERA	2
Numerical Simulation of Wall Condensation from a Superheated Steam and Air Mixture in a Vertical Pipe	2
Flow-Induced Vibration Experiment in Fuel Pin Bundle with Heavy Liquid Metal Flow: Test Section Design and Measurement Methods	2
Organic Telluride Formation from Paint Solvents Under Gamma Irradiation	2
Fermi at Trinity	2
Evaluation of Sodium Radioactivity in the Primary System of the Prototype Fast Reactor Monju	2
Improving Pulse Shape Discrimination in Organic Scintillation Detectors by Understanding Underlying Data Structure	2
Cognitive Aging as a Human Factor: Effects of Age on Human Performance	2
An Assessment of Deep Borehole Disposal Post-Closure Safety	2
Cost- and Risk-Based Seismic Design Optimization of Nuclear Power Plant Safety Systems	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
Microstructural and Mechanical Properties of Nitrogen Ion Irradiated 316 Stainless Steel	2
Release Behaviors of Elements from an Ag-In-Cd Control Rod Alloy at Temperatures up to 1673 K	2
ATHLET Simulation of PKL I2.2 IB-LOCA Benchmark Test and Quantitative Assessment	2