OOIR: Observatory of International Research

Papers

(The median citation count of Nuclear Technology is 0. 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 2021-02-01 to 2025-02-01.)

Article	Citations
Experimental Measurement and Multiphysics Simulation of Tritium Transport in Neutron-Irradiated Flibe Salt	102
Rewetting Delay Time During Jet Impingement Quench Cooling of Hot Curved Surfaces	41
Neutronic Performance Analysis of Inner-Side Chromium Coatings for Accident Tolerant Fuel	40
Recent ²³⁸Pu Production Activities at Idaho National Laboratory	38
Computational Optimization of ^{133 m} Xe Production in the Washington State University TRIGA Reactor	28
Hybrid System Level and Coarse Grid CFD Tool for Three-Dimensional Natural Circulation, Mixing, and Stratification Modeling	28
Thermal-Hydraulic Core Design of a Thorium-Based Molten Salt Fast Energy Amplifier	27
Preferable Applications of Best-Estimate Plus Uncertainty Under a Technology-Inclusive, Risk-Informed Nuclear Plant Safety Case	18
Scoping Studies of Reactor Core Parameters in Support of the Abilene Christian University Molten Salt Research Reactor	16
Design of a Low-Enrichment Uranium Reactor to Power a Future Martian Colony	16
On the Language of Reliability: A System Engineer Perspective	15
Code Validation of SAM Using Forced and Natural Circulation Data from NACIE-UP Benchmark	14
Experimental Study on Aerosol and Gas Emission of Solvent Fire Accident in Nuclear Fuel Cycle Facility	13
First Experimental Demonstration of the Use of a Novel Planar Segmented HPGe Detector for Gamma Emission Tomography of Mockup Fuel Rods	12
Airborne Release Fraction of Dissolved Materials During the Combustion of Liquids Representative of Nuclear Waste Treatment Process	12
Numerical Investigation into the Temperature Profile of a PHWR Channel Containing a Disassembled Fuel Bundle During a Postulated Accident Condition	12
A Method for Monitoring and Evaluating the Management of a Nuclear Regulatory Body Using a New Approach for Cross-Cutting Indicators	12
Examining Low-Energy Gamma-Ray Protection of a New Promising Saudi Cement Product as Alternative Cementitious Material Using Geant4 Software	10
Short-Term Assessment of Radiological Impact and Potential Risk to Workers and Public from Argonaut Nuclear Reactor Accidental Release	10
Measurement of Local Void Fraction of Air-Water Flow in an 8 × 8 Rod Bundle Using High-Resolution Gamma-Ray Tomography	10
Validation of Pronghorn Pressure Drop Correlations Against Pebble Bed Experiments	10
Pore Forming Agent–Assisted Fabrication of Porous Platinum Vent Frits and Their Suitability Evaluation for Radioisotope Power Sources	10
Separation of Flux/Dose Contributions from Multiple Transport Pathways in Monte Carlo Shielding Analyses of a Consolidated Interim Spent Nuclear Fuel Storage Facility	9
Foreword: Selected papers from the 2020 International Topical Meeting on Advances in Thermal Hydraulics (ATH’20)	9
Modeling Microreactor Requirements for High-Performance Computing	9

Verification and Demonstration of One-Dimensional Freezing Model in SAM for Salt-Cooled Reactor Analysis Applications	9
Development of an Epoxy Solidification Method for Radioactive Spent Resins	9
In Situ Chlorine Generation and Rare Earth Chlorination by Molten Salt Electrolysis	9
Rudolf Peierls’s “Outline of the Development of the British Tube Alloy Project”: A 1945 Account of the Earliest UK Work on Atomic Energy	9
Investigation of the Transfer Rate of Radioactive Materials in a Hydrogen Explosion Accident at a Reprocessing Plant	9
Coupling Gothic and RELAP5 for Passive Containment Cooling Modeling	8
Model Development for Thermal-Hydrology Simulations of a Full-Scale Heater Experiment in Opalinus Clay	8
Geant4 Extension for Neutronic Calculation of Nuclear Reactor Core	8
Reliability Evaluation of Complex Nuclear Energy Redundancy Systems with Atypical Time-Distribution Events	8
Multiphysics Analyses of the Bottom Components of the 3D Printed Transformational Challenge Reactor	8
Adsorption of Radioactive Iodine Using Nanocarbon on ETS-10 as Adsorbent	8
Cherenkov Glass Detectors with Wavelength Shifting Fibers for Neutron Measurements	8
An Assessment of Deep Borehole Disposal Post-Closure Safety	8
Best Estimate Plus Uncertainty Analysis of Station Blackout Transient in Pool-Type Research Reactor	8
Optimization Studies of Elemental Composition of Composite Polymer for Neutron Shielding Using Factorial Design Analysis	7
Reactor Performance and Safety Characteristics of Beryllium-Based Composite Moderators as Replacements for Graphite in mHTGRs	7
Feasibility Assessment of a Natural-Circulation Salt Irradiation Loop in the Advanced Test Reactor	7
Estimation of Pipe Wall Thinning Using a Convolutional Neural Network for Regression	7
Flow Regime Classification in Hexagonal Wire-Wrapped Fuel Assembly Using Advanced Machine Learning Models	7
Simplified Assessment Methodology of Radionuclide Contamination for Subsurface Soil	7
Radiation Compatibility of Geopolymer, Polymer, and Composite Materials for Use as Inner Shielding in Radioactive Waste Containers—A Simulation-Based Study	7
Foreword: Special issue on Heavy Liquid Metal–Cooled Fast Reactor Technology	6
Participatory Development of Virtual Reality Training for Nuclear Power Plant Field Operators	6
Uncertainty-Aware and Explainable Human Error Detection in the Operation of Nuclear Power Plants	6
Revisiting Safety Culture: The Benefits of a New Cultural Analysis Framework for Safety Management	6
Coupling of CTF and RELAP5-3D Within an Enhanced-Fidelity Nuclear Power Plant Simulator	6
Release Behaviors of Elements from an Ag-In-Cd Control Rod Alloy at Temperatures up to 1673 K	6
Gamma Radiation Shielding Assessment Using Stochastic, Deterministic, and Experimental Methods for RBMK-1500 SNF Storage Cask	6
Protected Loss-of-Flow Accident in a HLM Pool Facility: Long-Term Cooling Experiment	6
Research on the Performance of Nuclear Battery with SiC-Schottky and GaN-PIN Structure	6
The Effect of Fuel Aerosol Particle Size on Aerosol Release Potential in Energetic Core Disruptive Accident Studies	6
Numerical and Experimental Vibration Analysis of an Additive Manufactured Sensor Mounting Unit for a Wireless Valve Position Indication Sensor System	6
Development of Whole System Digital Twins for Advanced Reactors: Leveraging Graph Neural Networks and SAM Simulations	6
Transient Current Analysis of GaN Neutron Detector Based on the SRIM and TCAD Methods	6
Surface-Activated Graphite Oxide Nanosheets with Promoted U(VI) Adsorption Performance	6
“Economizing” TEPCO’s Responsibility for the Fukushima Daiichi Nuclear Power Plant Accident	5
On the Origins of Lagrangian Hydrodynamic Methods	5
Phenomenon Identification and Ranking Table Development for Future Application Figure-of-Merit Studies on Thermal Energy Storage Integrations with Light Water Reactors	5
High-Resolution X-Ray Radiography Methods Developed for Post-CHF Experiment	5
Lead Fast Reactor Thermal-Hydraulic Testing Facilities in Support of the UK Advanced Modular Reactor Program	5
Woolwich, Bruceton, Los Alamos: Munroe Jets and the Trinity Gadget	5
Experiment and Modeling of Interfacial Area Concentration of Liquid Film in Upward Annular Two-Phase Flow	5
Foreword: Special issue on the U.S. Department of Energy Microreactor Program	5
Modeling of OECD/NEA P2M Benchmark Cases by Means of TRANSURANUS Code	5
The Manhattan Project Nuclear Science and Technology Developments at Los Alamos: A Special Issue of Nuclear Technology	5
Neutronics and Thermo-Fluids Simulation of Generic Pebble-Bed Fluoride-Salt-Cooled High-Temperature Reactor	5
Numerical Simulation and Validation of Debris Bed Self-Leveling Behavior with Mixed-Density Particles Using CFD-DEM Coupling Algorithm	5
Experiments on Slug Flow Dynamics in Helically Coiled Tubes	5
Calculation of Isotope-Specific Fission Rates for Neutrino Source Calculation in PWR Fuel Diversion Safeguarding	4
Steady-State In-Pile Nuclear Thermal Propulsion Experimental Testbed Initial Demonstration at The Ohio State University Research Reactor	4

The Trinity High-Explosive Implosion System: The Foundation for Precision Explosive Applications	4
REMADA: An Emergency Decision-Making Software for Radiation Dose Estimation of Mitigation Tasks in a Reactor Building During Severe Nuclear Accidents	4
Determining the Position of Gamma-Ray Interaction Using Large Scintillation Detectors and the Least Number of Photomultiplier Tubes	4
Spatiotemporal Evaluation of Bubble Characteristics in Sodium Using Real-Time X-Ray Imaging	4
Equation of State: Manhattan Project Developments and Beyond	4
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	4
Nuclear Data Uncertainty Propagation in the PWR MOX/UO2 Core Transient Benchmark	4
Application of Cable Condition Monitoring Technologies to Assess Age-Related Degradation of Industrial Cables Installed in Harsh Environments	4
Nonhomogeneous Poisson Process Model for Estimating Mean Time Between Failures of the JE01-AP03 Primary Pump Implemented on the RSG-GAS Reactor	4
A Review of Remote Welding and Nondestructive Examination Technologies for the DOE Standard Canister	4
Safety Assessment Methodology for Transportation of Radioactive Material via Train	4
Performance Analysis of Water Heat Pipe for Application of the Passive Cooling System in Nuclear Power Plants	4
Canadian Contributions to the Manhattan Project and Early Nuclear Research	4
Design and Development of a Portable Neutron Detection System Based on a ⁶ Li-Doped ZnS(Ag) Scintillator	4
TRISO Fuel’s Safety Functions, Contributions to Reactor Safety, and Necessary Safety Limits	4
Artificial Intelligence Detection System of Radioactive Nanocomposites in Liquid-Filled Containers for Nuclear Security	4
Enhanced Bentonite/PVA Matrix for Advanced Shielding Applications	4
Neutronics Calculation Advances at Los Alamos: Manhattan Project to Monte Carlo	4
Risk, “Radiophobia,” and Social Learning: Applying Lessons from the Literature	4
Analysis of Ductile-to-Brittle Transition Characteristics of Reactor Pressure Vessel Steels	4
Comparison Between Historic Nuclear Explosion Yield Formulas	4
STORAGE: A Source Term Model for Intermediate-Level Radioactive Waste	4
Availability of Critical Benchmark Experiments for the Pebble Tanker Transportation Model for Nuclear Criticality Safety Validation of TRISO Pebbles	4
Space Nuclear Propulsion Fuel and Moderator Development Plan Conceptual Testing Reference Design	3
A Review on the Development of Single-Moderator-Based Neutron Spectrometers	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
Adsorption Properties of Cs(I) and Co(II) on GMZ Bentonite Colloids	3
Criticality Experiments with Fast ²³⁵U and ²³⁹Pu Metal and Hydride Systems During the Manhattan Project	3
Liquid Film Thickness for Gas-Liquid Annular Flow Across Grid Spacer with Vanes in Simple 3 × 3 Rod Bundle Channel	3
Verification of the SAM Code by Means of the Method of Manufactured Solutions: Application to Molten Salt Reactor Multiphysics Simulation	3
Conceptual Design of a Micro Nuclear Reactor for Canadian Arctic Communities	3
Exhaustive Test Case Generation for Nuclear Safety Software Based on the Software Logic Model	3
Evaluation of Fuel Reactivity Worth Measurement in the Prototype Fast Reactor Monju	3
Highly Available Nuclear Power in a Microgrid Configuration for the ORNL Distribution System	3
Numerical Study on Subcooled Boiling Flow and Heat Transfer Characteristics in Helical Cruciform Fuel Assembly	3
Neutronic Analysis of the Conceptual Molten Uranium Breeder Reactor Using MCNP and SCALE Tools	3
Application of Artificial Intelligence in Detection and Mitigation of Human Factor Errors in Nuclear Power Plants: A Review	3
Modeling of an Energy-Diverse Embedded Grid for Microreactor Integration	3
Progress in Fast Modular Reactor Conceptual Design	3
Advanced Reactor Control and Operations (ARCO): A University Research Facility for Developing Optimized Digital Control Rooms	3
A New Method to Efficiently Estimate the Equilibrium State of Pebble Bed Reactors	3
Addressing Human and Organizational Factors in Nuclear Industry Modernization: A Sociotechnically Based Strategic Framework	3
Core Modeling and Simulation of Peach Bottom 2 Turbine Trip Test 2 Using CASMO5/TRACE/PARCS	3
In-Canal Assay of High Specific Activity ⁶⁰Co at the Advanced Test Reactor	3
Analysis of Influence of Tube Failure on Performance of Passive Residual Heat Removal Heat Exchanger	3
The Origins of Blast-Loaded Vessels	3
Editor’s Note	3
Estimated Radiation Doses and Projected Cancer Risks for New Mexico Residents from Exposure to Radioactive Fallout from the Trinity Nuclear Test	3
Surrogate Model of Solved Poisson Kriging Method for Radiation Field Reconstruction	3
Correlation Method of 3-D Detection of Distant Sources of Gamma Radiation and Neutrinos by Intensity Interferometry	3
Characterization and Modeling of Gravity-Driven Flashing of Superheated Water in a Pool Heated from Below	3
Nuclear Power Concepts and Development Strategies for High-Power Electric Propulsion Missions to Mars	3
Design and Analysis of an Internal Remote Monitoring System for Spent Nuclear Fuel Stored in a Dry Cask	3
Improving Pulse Shape Discrimination in Organic Scintillation Detectors by Understanding Underlying Data Structure	3
Removal Effectiveness for Washing Ce(IV), U(VI), and Zr(IV) Ions from Contaminated Purex Solvent by Hydrazine Carbonate	3
Delayed Heating Calculations Using the MCNP-ORIGEN Activation Automation Tool	3
Technical Reviewers	3
Development of a Signal Processing Software for Scintillation Detectors and Implementation on an FPGA for Fast Sensing	3
Risk Plus Some Attributes (R + SA): A New Risk-Informed Method for Prioritizing Inspection Activities During New Fuel Facility Construction	3
High-Resolution Gamma-Ray Spectrometry of Pebble Bed Reactor Fuel Using Adaptive Digital Pulse Processing	3
Development and Test Results of Thermocouples Used in the TRISO-Fuel Irradiation Experiment AGR-5/6/7	3
Core Study of 5-MW(thermal) Water-Cooled Super Small Modular Reactor (WSMR) Based on the Sensitivity Analysis of the Key Design Parameters for Operation	3
The Carbon Value of Nuclear Power Plant Lifetime Extensions in the United States	3
Turbulent Particle Flow in Spent Nuclear Fuel Storage Systems	3
Comments on the Frisch-Peierls Estimate of the Critical Mass of a Uranium Fission Bomb	3
Application of Systems Usability Case in an Integrated System Validation of Control Room	2
Plutonium-238 Production Program Results, Implications, and Projections from Irradiation and Examination of Initial NpO₂ Test Targets for Improved Production	2
Analysis of the Neutron Radiographic Image Quality and Beam Intensity Produced by a Compact Multichannel Collimator	2
Toward an In-Depth Material Model for Cermet Nuclear Thermal Rocket Fuel Elements	2
Effect of Nb Addition on Corrosion Resistance of U-6Zr Alloys	2
The MOOSE Multiphysics Computational Framework for Nuclear Power Applications: A Special Issue of Nuclear Technology	2
Comparison of Two Methods for Obtaining the Variabilities in a FRAM Model of a Combined Nuclear Facility Project	2
Two-Fluid and Discrete Population Balance Model for Simulation of Batch Sedimentation Relevant to Plutonium Reconversion	2
Revisiting Mobile Paste Reactor Fuel	2
Incorporating the Effect of Centrifugal Force into the Correlation for Saturated Flow Boiling Heat Transfer in a Helically Coiled Tube	2
Structural Ignorance of Expertise in Nuclear Safety Controversies: Case Analysis of Post-Fukushima Japan	2
Prolonged Operation of Hydro-Accumulators in VVER-1000/V446 Considering Flow Restriction Components	2
Treatment of Simulated Radioactive Wastewater Using Reverse Osmosis and Membrane Distillation	2
Commentary	2
Lightweight Heat Pipe Radiator for Nuclear Reactor Power Systems on Lunar Surface	2

Fluid Dynamics Effects of a Porous Blockage on Laminar Flow in the Interior Subchannels of a 61-Pin Wire-Wrapped Rod Bundle	2
An Experimental and Theoretical Examination of Air Ingress Rates During Small- and Medium-Break Air Ingress Accidents	2
Analysis on Fire-Retardant Performance of non–Class 1E Cables Depending on the Ambient Temperature Condition Surrounding the Facilities for Flame Test of Cables	2
Modeling and Optimization of ¹⁴⁷ Pm Radioisotope-Powered GaN-Based PIN Junction Betavoltaic Cell	2
Overview and Recommendations for Cyber Risk Assessment in Nuclear Power Plants	2
An Optimal Radiation Shield Design of a Small Modular Nuclear Power Reactor by Genetic Algorithm	2
Guiding Transformation: The Role of a Design Philosophy	2
A Methodology to Support the Development of a New State Vision for the U.S. Nuclear Industry	2
Research on Active Disturbance Rejection Control of Small Modular Reactor Once-Through Steam Generator Based on Differential Evolution Optimization Algorithm	2
Enhancement of Fast Neutron Detection in Liquid Scintillator Detectors	2
Failure Analysis of CRDINiCr Butterfly Valves for Nuclear Power Plant Applications	2
Molybdenum-99 from Molten Salt Reactor as a Source of Technetium-99m for Nuclear Medicine: Past, Current, and Future of Molybdenum-99	2
Covert Cognizance: A Novel Predictive Modeling Paradigm	2
Development of a New Thermal-Hydraulic Module for FRENETIC, a Code for the Multiphysics Analysis of Liquid Metal–Cooled Reactors	2
A Monte Carlo Study for Soft Tissue Equivalency of Potential Polymeric Biomaterials Used in Carbon Ion Radiation Therapy	2
Shielding Analysis for a Moderated Low-Enriched-Uranium–Fueled Kilopower Reactor	2
Monte Carlo Analysis of Coolant Stream Impurity Gamma Emissions in Gas-Cooled Fast Reactors	2
Modeling of the P2M Past Fuel Melting Experiments with the Fuel Performance Code FAST-1.0.1	2
Measurement of the Effective Capture Cross Section of ²³⁸Np in the High Flux Isotope Reactor	2
Feasibility of a Small, Low-Power RTG Concept Utilizing a GPHS Heat Source	2
Considerations for Implementing Presidential Memorandum-20 Guidelines for Nuclear Safety Launch Authorization for Future Civil Space Missions	2
Convolutional Neural Network–Aided Temperature Field Reconstruction: An Innovative Method for Advanced Reactor Monitoring	2
A Framework for Event Detection in Nuclear Facilities Using Wireless Sensors and Actors Networks	2
Natural Analogue Studies in Support of Post-Closure Safety Assessment of Deep Geological Disposal	2
Experimental Results of PbLi-Water Reaction Performed in LIFUS5/Mod3 Separate Effect Test Facility	2
Predictive Modeling of a Simple Field Matrix Diffusion Experiment Addressing Radionuclide Transport in Fractured Rock. Is It So Straightforward?	2
Foreword: Selected papers from the 2021 Nuclear and Emerging Technologies for Space Topical Meeting (NETS 2021)	2
Numerical Simulation of Wall Condensation from a Superheated Steam and Air Mixture in a Vertical Pipe	2
Preliminary Modeling of Chloride Deposition on Spent Nuclear Fuel Canisters in Dry Storage Relevant to Stress Corrosion Cracking	2
Newly Developed Method for Liquid Thin Film Thickness Measurement Using Optical Fiber–Based Reflective Probe	2
Experimental Analysis of Steam Generator Tube Rupture in CIRCE Facility for MYRRHA Configuration	2
Comparative Study of Raman and EPMA Elemental Mapping of an Unirradiated MOX Sample	2
Discrete Element Method Simulation of Vibratory Filling of Convoluted Hot Isostatic Pressing Canisters Using Idaho Calcine Waste Simulant	2
Organic Telluride Formation from Paint Solvents Under Gamma Irradiation	2
Fuel Melting Simulation with FRAPCON/FRAPTRAN Codes for the Power-to-Melt-and-Maneuverability Simulation Exercise and Consideration of Model Modifications	2
Operation Cycle Length Extension of a Konvoi PWR: Requirements and Experience from Operator’s Viewpoint	2
Extrapolation of Monte Carlo–Derived Noble Gas Air-Submersion Effective Dose Rate Coefficients for Selected Occupational Settings to Other Geometries and Radionuclides	2
Examination of Deep Learning Algorithm for Nuclear Proliferation Risk Modeling	2
Feasibility Analysis of Tritium Measurement in the Aqueous Medium Based on a Plastic Scintillating Fiber Array	2
Integral-Effect Test for Loss of Residual Heat Removal System During Mid-Loop Operation in ATLAS Facility	2
Investigation of Machine Learning Regression Techniques to Predict Critical Heat Flux Over a Large Parameter Space	2
Foreword: Special issue on the Power-to-Melt and Maneuverability (P2M) Simulation Exercise	2
Mankala Chronicles: Nuclear Energy Financing and Cooperative Corporate Form in Finland	2
Design and Assessment of the New CIRCE-THETIS Facility for the Development of Heavy Liquid Metal Cooled Fast Reactors	2
Numerical Investigation of Melting in Pressurized Water Reactor Fuel Rod Considering Operational Parameters of the Core	2
Inertial Effects and Anisotropy for the Flow in a Domain of Close Packed Spheres with a Bounding Wall	1
Implementation of a Drift Flux Model into SAM with Development of a Verification and Validation Test Suite for Modeling of Noncondensable Gas Mixtures	1
Sockeye: A One-Dimensional, Two-Phase, Compressible Flow Heat Pipe Application	1
Attractiveness of Fissile Material in Nuclear Wastes from Different Fuel Cycles	1
Initial Exploratory Reactor Physics Assessment of Nonconventional Fuel Concepts for Very Compact Small Modular Reactors Using Hydroxides as Coolants and/or Moderators	1
Exploring the Feasibility of Kuiper Belt Missions Supported by Centrifugal Nuclear Thermal Propulsion	1
Thermal-Hydraulic Research Supporting the Development of SMART	1
Advanced Instrumentation and Modeling Framework for Two-Phase Flow	1
Sequential Deployment of Mobile Radiation Sensor Network Using Reinforcement Learning in Radioactive Source Search	1
Direct Dissolution of Used Nuclear Fuel in PUREX Solvent: Review and Flowsheet Development	1
Foreword: Selected papers from the NPIC&HMIT 2019 and 2021 Topical Meetings	1
Effects of Impurities and Additives on Interactions of Nuclear-Grade Graphite with Molten LiF-NaF-KF	1
Study of External Source Effects for Different Multibeam Concept for Accelerator-Driven Subcritical Reactor for Nuclear Waste Transmutation (ADS-NWT)	1
Multi-Mission Thermoelectric Generator Fueling Testing and Integration Operations for Mars 2020	1
Validation Matrix for Pool Scrubbing Models	1
Differential Pressure Changes of a High Airflow–Type HEPA Filter During Solvent Fire in Reprocessing Facilities	1
Nuclear Reactor Operations Education and Training with Virtual Reality and an Immersive Desktop Application	1
Experimental Simulation of Decay Heat of Corium at the Lava-B Test-Bench	1
Investigation of Lunar Shallow Subsurface Water Content and Soil Elemental Composition via Active Neutron Detection	1
CFD Modeling of Aerosol Transport and Deposition Using a Drift-Flux Model	1
A RELAP5-3D Model of the Lobo Lead Loop	1
Cognitive Aging as a Human Factor: Effects of Age on Human Performance	1
PHWR Reactivity Device Incremental Macroscopic Cross Sections and Reactivities for a Molybdenum-Producing Bundle and a Standard Bundle	1
Transitioning to a Sustainable Thorium Fuel Cycle in Pressurized Water Reactors Using Bimetallic Thorium-Zirconium Alloy Cladding	1
Relation Between the Characteristic X-Ray Intensity and Incident Electron Energy Using the Monte Carlo Method and Measurements	1
Technical Reviewers	1
Evaluation of Control Rod Interaction Measurement in the Prototype Fast Reactor Monju	1
Density Equation for Mixed Organic Solutions Containing tri- n -butyl Nitrate, n -Dodecane, Nitric Acid, and Nitrates of Heavy Metals	1
Experimental Model to Study Characteristics of Radon Cover in Waste Landfills	1
MSR Transient Simulation and MSRE Transient Benchmark with SAM and SPECTRA	1
Cross-Section Calculations for the Production of ¹²³I and ¹²⁴I Radioisotopes via (p,n) and (p,2n) Reactions Using Collective Nuclear Level Density Model	1
Shield Design of the First Protective Collimator in the METU-Defocusing Beamline (DBL) Project	1
State-of-the-Art Reactor Consequence Analyses Project: Uncertainty Analyses for Station Blackout Scenarios	1
Estimation Method for Residual Sodium Amount on Unloaded Dummy Fuel Assembly	1
Pressure Drop Correlation Improvement for the Near-Wall Region of Pebble-Bed Reactors	1
The Taming of Plutonium: Plutonium Metallurgy and the Manhattan Project	1
Partial Cross-Section Calculations for PGNAA Based on a Deterministic Neutron Transport Solver	1
Response to the Seawater Contamination Event at Hamaoka Unit 5 and the Effects of Corrosion by Seawater	1
Optimized FSF Controller for Bulk Power Control of Large-Core PHWRs	1
Foundations for a Fission Battery Digital Twin	1
Interphase and Intergroup Mass Transfer in the Two-Group Two-Fluid Model in Flows with Phase Change	1
Identification of Carbon in Glassy Cesium-Bearing Microparticles Using Electron Microscopy and Formation Mechanisms of the Microparticles	1
Void Fraction and Interfacial Friction in Vertical Circular Pipes with the Square Top End Under Flooding Conditions	1
A Structural Design Approach Tailored for the Rapid Preliminary Design of Microreactor Components	1
Development of Two-Step Method for Fast Chloride MSR Neutronics	1
Determination of Gain Scheduling Parameters for Loss of a Feedwater Pump Transient Mitigation Using Neural Networks	1
Exploring Public Discourse About Spent Nuclear Fuel Management on Twitter	1
Safety-Related Instrumentation and Control Pilot Upgrade: Initial Scoping Phase Implementation and Lessons Learned	1
One-Dimensional Steady-State Thermal Model of CNTP Reactor	1
Parametric Analysis of an Optical Fiber–Based Gamma Thermometer for University Research Reactors Using an Analytic Thermal Model	1