Nuclear Technology

Article	Citations
Experimental Measurement and Multiphysics Simulation of Tritium Transport in Neutron-Irradiated Flibe Salt	48
Neutronic Performance Analysis of Inner-Side Chromium Coatings for Accident Tolerant Fuel	46
Recent 238Pu Production Activities at Idaho National Laboratory	39
Safety Assessment Methodology for Transportation of Radioactive Material via Train	18
Preferable Applications of Best-Estimate Plus Uncertainty Under a Technology-Inclusive, Risk-Informed Nuclear Plant Safety Case	18
Computational Optimization of 133 m Xe Production in the Washington State University TRIGA Reactor	18
Hybrid System Level and Coarse Grid CFD Tool for Three-Dimensional Natural Circulation, Mixing, and Stratification Modeling	18
Nonhomogeneous Poisson Process Model for Estimating Mean Time Between Failures of the JE01-AP03 Primary Pump Implemented on the RSG-GAS Reactor	17
Examining Low-Energy Gamma-Ray Protection of a New Cement Product as an Alternative Cementitious Material Using Geant4 Software	16
A Review on the Development of Single-Moderator-Based Neutron Spectrometers	16
Scoping Studies of Reactor Core Parameters in Support of the Abilene Christian University Molten Salt Research Reactor	13
Airborne Release Fraction of Dissolved Materials During the Combustion of Liquids Representative of Nuclear Waste Treatment Process	13
On the Language of Reliability: A System Engineer Perspective	13
Experimental Study on Aerosol and Gas Emission of Solvent Fire Accident in Nuclear Fuel Cycle Facility	13
Code Validation of SAM Using Forced and Natural Circulation Data from NACIE-UP Benchmark	13
A Method for Monitoring and Evaluating the Management of a Nuclear Regulatory Body Using a New Approach for Cross-Cutting Indicators	12
Pore Forming Agent–Assisted Fabrication of Porous Platinum Vent Frits and Their Suitability Evaluation for Radioisotope Power Sources	11
Numerical Investigation into the Temperature Profile of a PHWR Channel Containing a Disassembled Fuel Bundle During a Postulated Accident Condition	11
High-Resolution X-Ray Radiography Methods Developed for Post-CHF Experiment	10
Radiation Compatibility of Geopolymer, Polymer, and Composite Materials for Use as Inner Shielding in Radioactive Waste Containers—A Simulation-Based Study	10
Rewetting Delay Time During Jet Impingement Quench Cooling of Hot Curved Surfaces	10
Validation of Pronghorn Pressure Drop Correlations Against Pebble Bed Experiments	10
Estimation of Pipe Wall Thinning Using a Convolutional Neural Network for Regression	10
Steady-State In-Pile Nuclear Thermal Propulsion Experimental Testbed Initial Demonstration at The Ohio State University Research Reactor	10
Thermal-Hydraulic Core Design of a Thorium-Based Molten Salt Fast Energy Amplifier	10

Canadian Contributions to the Manhattan Project and Early Nuclear Research	10
Space Nuclear Propulsion Fuel and Moderator Development Plan Conceptual Testing Reference Design	10
Protected Loss-of-Flow Accident in a HLM Pool Facility: Long-Term Cooling Experiment	9
Reliability Evaluation of Complex Nuclear Energy Redundancy Systems with Atypical Time-Distribution Events	9
Application of Artificial Intelligence in Detection and Mitigation of Human Factor Errors in Nuclear Power Plants: A Review	9
In Situ Chlorine Generation and Rare Earth Chlorination by Molten Salt Electrolysis	9
Comparison Between Historic Nuclear Explosion Yield Formulas	9
Equation of State: Manhattan Project Developments and Beyond	8
Design of a Low-Enrichment Uranium Reactor to Power a Future Martian Colony	8
Modeling of an Energy-Diverse Embedded Grid for Microreactor Integration	8
Simplified Assessment Methodology of Radionuclide Contamination for Subsurface Soil	8
Numerical and Experimental Vibration Analysis of an Additive Manufactured Sensor Mounting Unit for a Wireless Valve Position Indication Sensor System	8
Coupling of CTF and RELAP5-3D Within an Enhanced-Fidelity Nuclear Power Plant Simulator	8
Reactor Performance and Safety Characteristics of Beryllium-Based Composite Moderators as Replacements for Graphite in mHTGRs	7
REMADA: An Emergency Decision-Making Software for Radiation Dose Estimation of Mitigation Tasks in a Reactor Building During Severe Nuclear Accidents	7
Modeling Microreactor Requirements for High-Performance Computing	7
Adsorption of Radioactive Iodine Using Nanocarbon on ETS-10 as Adsorbent	7
An Assessment of Deep Borehole Disposal Post-Closure Safety	7
Multiphysics Analyses of the Bottom Components of the 3D Printed Transformational Challenge Reactor	7
First Experimental Demonstration of the Use of a Novel Planar Segmented HPGe Detector for Gamma Emission Tomography of Mockup Fuel Rods	7
Measurement of Local Void Fraction of Air-Water Flow in an 8 × 8 Rod Bundle Using High-Resolution Gamma-Ray Tomography	7
Determining the Position of Gamma-Ray Interaction Using Large Scintillation Detectors and the Least Number of Photomultiplier Tubes	6
Foreword: Selected papers from the 2020 International Topical Meeting on Advances in Thermal Hydraulics (ATH’20)	6
Separation of Flux/Dose Contributions from Multiple Transport Pathways in Monte Carlo Shielding Analyses of a Consolidated Interim Spent Nuclear Fuel Storage Facility	6
Investigation of the Transfer Rate of Radioactive Materials in a Hydrogen Explosion Accident at a Reprocessing Plant	6
Risk, “Radiophobia,” and Social Learning: Applying Lessons from the Literature	6
Verification and Demonstration of One-Dimensional Freezing Model in SAM for Salt-Cooled Reactor Analysis Applications	6
Best Estimate Plus Uncertainty Analysis of Station Blackout Transient in Pool-Type Research Reactor	6
Rudolf Peierls’s “Outline of the Development of the British Tube Alloy Project”: A 1945 Account of the Earliest UK Work on Atomic Energy	6
Short-Term Assessment of Radiological Impact and Potential Risk to Workers and Public from Argonaut Nuclear Reactor Accidental Release	6
Model Development for Thermal-Hydrology Simulations of a Full-Scale Heater Experiment in Opalinus Clay	6
Transient Current Analysis of GaN Neutron Detector Based on the SRIM and TCAD Methods	5
“Economizing” TEPCO’s Responsibility for the Fukushima Daiichi Nuclear Power Plant Accident	5
Woolwich, Bruceton, Los Alamos: Munroe Jets and the Trinity Gadget	5
Cherenkov Glass Detectors with Wavelength Shifting Fibers for Neutron Measurements	5
Foreword: Special issue on Heavy Liquid Metal–Cooled Fast Reactor Technology	5
Optimization Studies of Elemental Composition of Composite Polymer for Neutron Shielding Using Factorial Design Analysis	5
Lead Fast Reactor Thermal-Hydraulic Testing Facilities in Support of the UK Advanced Modular Reactor Program	5
Modeling of OECD/NEA P2M Benchmark Cases by Means of TRANSURANUS Code	5
Participatory Development of Virtual Reality Training for Nuclear Power Plant Field Operators	5
Research on the Performance of Nuclear Battery with SiC-Schottky and GaN-PIN Structure	5
Release Behaviors of Elements from an Ag-In-Cd Control Rod Alloy at Temperatures up to 1673 K	5
Gamma Radiation Shielding Assessment Using Stochastic, Deterministic, and Experimental Methods for RBMK-1500 SNF Storage Cask	5
The Manhattan Project Nuclear Science and Technology Developments at Los Alamos: A Special Issue of Nuclear Technology	5
Development of Whole System Digital Twins for Advanced Reactors: Leveraging Graph Neural Networks and SAM Simulations	5
Geant4 Extension for Neutronic Calculation of Nuclear Reactor Core	5
The Effect of Fuel Aerosol Particle Size on Aerosol Release Potential in Energetic Core Disruptive Accident Studies	5
Turbulent Particle Flow in Spent Nuclear Fuel Storage Systems	4
Numerical Simulation and Validation of Debris Bed Self-Leveling Behavior with Mixed-Density Particles Using CFD-DEM Coupling Algorithm	4
Experiments on Slug Flow Dynamics in Helically Coiled Tubes	4

Flow Regime Classification in Hexagonal Wire-Wrapped Fuel Assembly Using Advanced Machine Learning Models	4
Nuclear Data Uncertainty Propagation in the PWR MOX/UO2 Core Transient Benchmark	4
A Review of Remote Welding and Nondestructive Examination Technologies for the DOE Standard Canister	4
STORAGE: A Source Term Model for Intermediate-Level Radioactive Waste	4
TRISO Fuel’s Safety Functions, Contributions to Reactor Safety, and Necessary Safety Limits	4
Availability of Critical Benchmark Experiments for the Pebble Tanker Transportation Model for Nuclear Criticality Safety Validation of TRISO Pebbles	4
Risk Plus Some Attributes (R + SA): A New Risk-Informed Method for Prioritizing Inspection Activities During New Fuel Facility Construction	4
Phenomenon Identification and Ranking Table Development for Future Application Figure-of-Merit Studies on Thermal Energy Storage Integrations with Light Water Reactors	4
Uncertainty-Aware and Explainable Human Error Detection in the Operation of Nuclear Power Plants	4
Experiment and Modeling of Interfacial Area Concentration of Liquid Film in Upward Annular Two-Phase Flow	4
Enhanced Bentonite/PVA Matrix for Advanced Shielding Applications	4
Verification and Validation of Depletion Calculations for TRISO Fuel Against Data from the Second Advanced Gas Reactor Irradiation Campaign	4
Spatiotemporal Evaluation of Bubble Characteristics in Sodium Using Real-Time X-Ray Imaging	4
Calculation of Isotope-Specific Fission Rates for Neutrino Source Calculation in PWR Fuel Diversion Safeguarding	4
Investigation of the Effects of Magnesium, Iron, and Manganese on Gamma Permeability in Zinc-Based Alloys Produced by Powder Metallurgy	4
Foreword: Special issue on the U.S. Department of Energy Microreactor Program	4
Artificial Intelligence Detection System of Radioactive Nanocomposites in Liquid-Filled Containers for Nuclear Security	4
Neutronics and Thermo-Fluids Simulation of Generic Pebble-Bed Fluoride-Salt-Cooled High-Temperature Reactor	4
Surface-Activated Graphite Oxide Nanosheets with Promoted U(VI) Adsorption Performance	4
The Trinity High-Explosive Implosion System: The Foundation for Precision Explosive Applications	4
Design and Development of a Portable Neutron Detection System Based on a 6 Li-Doped ZnS(Ag) Scintillator	4
Performance Analysis of Water Heat Pipe for Application of the Passive Cooling System in Nuclear Power Plants	4
Application of Cable Condition Monitoring Technologies to Assess Age-Related Degradation of Industrial Cables Installed in Harsh Environments	4
Neutronics Calculation Advances at Los Alamos: Manhattan Project to Monte Carlo	3
Neutronic Analysis of the Conceptual Molten Uranium Breeder Reactor Using MCNP and SCALE Tools	3
Progress in Fast Modular Reactor Conceptual Design	3
A New Method to Efficiently Estimate the Equilibrium State of Pebble Bed Reactors	3
Delayed Heating Calculations Using the MCNP-ORIGEN Activation Automation Tool	3
Incorporating the Effect of Centrifugal Force into the Correlation for Saturated Flow Boiling Heat Transfer in a Helically Coiled Tube	3
Analysis of Influence of Tube Failure on Performance of Passive Residual Heat Removal Heat Exchanger	3
Discrete Element Method Simulation of Vibratory Filling of Convoluted Hot Isostatic Pressing Canisters Using Idaho Calcine Waste Simulant	3
On the Origins of Lagrangian Hydrodynamic Methods	3
Development of a Signal Processing Software for Scintillation Detectors and Implementation on an FPGA for Fast Sensing	3
Advanced Reactor Control and Operations (ARCO): A University Research Facility for Developing Optimized Digital Control Rooms	3
High-Resolution Gamma-Ray Spectrometry of Pebble Bed Reactor Fuel Using Adaptive Digital Pulse Processing	3
Highly Available Nuclear Power in a Microgrid Configuration for the ORNL Distribution System	3
Liquid Film Thickness for Gas-Liquid Annular Flow Across Grid Spacer with Vanes in Simple 3 × 3 Rod Bundle Channel	3
Comments on the Frisch-Peierls Estimate of the Critical Mass of a Uranium Fission Bomb	3
Characterization and Modeling of Gravity-Driven Flashing of Superheated Water in a Pool Heated from Below	3
Design and Analysis of an Internal Remote Monitoring System for Spent Nuclear Fuel Stored in a Dry Cask	3
Nuclear Power Concepts and Development Strategies for High-Power Electric Propulsion Missions to Mars	3
Estimated Radiation Doses and Projected Cancer Risks for New Mexico Residents from Exposure to Radioactive Fallout from the Trinity Nuclear Test	3
Extrapolation of Monte Carlo–Derived Noble Gas Air-Submersion Effective Dose Rate Coefficients for Selected Occupational Settings to Other Geometries and Radionuclides	3
Technical Reviewers	3
Shielding Analysis for a Moderated Low-Enriched-Uranium–Fueled Kilopower Reactor	3
Replacement Strategy for Aging Nuclear Power Instrumentation and Control Equipment Based on Life Margin	3
Verification of the SAM Code by Means of the Method of Manufactured Solutions: Application to Molten Salt Reactor Multiphysics Simulation	3
Editor’s Note	3
Development and Test Results of Thermocouples Used in the TRISO-Fuel Irradiation Experiment AGR-5/6/7	3
Analysis of Ductile-to-Brittle Transition Characteristics of Reactor Pressure Vessel Steels	3
Surrogate Model of Solved Poisson Kriging Method for Radiation Field Reconstruction	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
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
Adsorption Properties of Cs(I) and Co(II) on GMZ Bentonite Colloids	3
Numerical Study on Subcooled Boiling Flow and Heat Transfer Characteristics in Helical Cruciform Fuel Assembly	3
Addressing Human and Organizational Factors in Nuclear Industry Modernization: A Sociotechnically Based Strategic Framework	3
Fluid Dynamics Effects of a Porous Blockage on Laminar Flow in the Interior Subchannels of a 61-Pin Wire-Wrapped Rod Bundle	3
Core Modeling and Simulation of Peach Bottom 2 Turbine Trip Test 2 Using CASMO5/TRACE/PARCS	3
Exhaustive Test Case Generation for Nuclear Safety Software Based on the Software Logic Model	3
Correlation Method of 3-D Detection of Distant Sources of Gamma Radiation and Neutrinos by Intensity Interferometry	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
Evaluation of Fuel Reactivity Worth Measurement in the Prototype Fast Reactor Monju	3
Fuel Melting Simulation with FRAPCON/FRAPTRAN Codes for the Power-to-Melt-and-Maneuverability Simulation Exercise and Consideration of Model Modifications	2
Preventing Reverse Engineering of Critical Industrial Data with DIOD	2
Analysis of a Selected Experiment of the OSU-MASLWR Test Facility Regarding Heat Transfer in Helically Coiled Steam Generators Using AC 2 -ATHLET	2
Correction	2
Development of a New Thermal-Hydraulic Module for FRENETIC, a Code for the Multiphysics Analysis of Liquid Metal–Cooled Reactors	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
Monte Carlo Analysis of Coolant Stream Impurity Gamma Emissions in Gas-Cooled Fast Reactors	2
Analysis of the Neutron Radiographic Image Quality and Beam Intensity Produced by a Compact Multichannel Collimator	2
Guiding Transformation: The Role of a Design Philosophy	2
Integral-Effect Test for Loss of Residual Heat Removal System During Mid-Loop Operation in ATLAS Facility	2
Predictive Modeling of a Simple Field Matrix Diffusion Experiment Addressing Radionuclide Transport in Fractured Rock. Is It So Straightforward?	2
Foreword: Special issue on the Power-to-Melt and Maneuverability (P2M) Simulation Exercise	2
A Monte Carlo Study for Soft Tissue Equivalency of Potential Polymeric Biomaterials Used in Carbon Ion Radiation Therapy	2
Measurement of the Effective Capture Cross Section of 238Np in the High Flux Isotope Reactor	2
Real-World Video Denoising for Visual Inspection in High-Dose Radiological Environments	2
Conceptual Design of a Micro Nuclear Reactor for Canadian Arctic Communities	2
Toward an In-Depth Material Model for Cermet Nuclear Thermal Rocket Fuel Elements	2
An Optimal Radiation Shield Design of a Small Modular Nuclear Power Reactor by Genetic Algorithm	2

Convolutional Neural Network–Aided Temperature Field Reconstruction: An Innovative Method for Advanced Reactor Monitoring	2
Experimental Analysis of Steam Generator Tube Rupture in CIRCE Facility for MYRRHA Configuration	2
Package Performance Study: A Historical Perspective and Planning for a Path Forward	2
A Methodology to Support the Development of a New State Vision for the U.S. Nuclear Industry	2
Mankala Chronicles: Nuclear Energy Financing and Cooperative Corporate Form in Finland	2
Experimental Results of PbLi-Water Reaction Performed in LIFUS5/Mod3 Separate Effect Test Facility	2
Parametric Analysis of the Compact and Long-Term-Operable Passive Residual Heat Removal System	2
Explanation of Deep Learning–Based Radioisotope Identifier for Plastic Scintillation Detector	2
Correction	2
Revisiting Mobile Paste Reactor Fuel	2
Preliminary Modeling of Chloride Deposition on Spent Nuclear Fuel Canisters in Dry Storage Relevant to Stress Corrosion Cracking	2
Study on Flow Characteristics of Integrated Natural Circulation Reactor Under Inclined Conditions	2
Natural Analogue Studies in Support of Post-Closure Safety Assessment of Deep Geological Disposal	2
Design and Assessment of the New CIRCE-THETIS Facility for the Development of Heavy Liquid Metal Cooled Fast Reactors	2
Overview and Recommendations for Cyber Risk Assessment in Nuclear Power Plants	2
A Redundancy-Guided Approach for the Hazard Analysis of Digital Instrumentation and Control Systems in Advanced Nuclear Power Plants	2
Commentary	2
Operation Cycle Length Extension of a Konvoi PWR: Requirements and Experience from Operator’s Viewpoint	2
Removal Effectiveness for Washing Ce(IV), U(VI), and Zr(IV) Ions from Contaminated Purex Solvent by Hydrazine Carbonate	2
Network Graph Laplacian-Based Sensor Projection in System-Level Modeling of Liquid-Metal Loop	2
Research on Active Disturbance Rejection Control of Small Modular Reactor Once-Through Steam Generator Based on Differential Evolution Optimization Algorithm	2
Investigation of Machine Learning Regression Techniques to Predict Critical Heat Flux Over a Large Parameter Space	2
Numerical Investigation of Melting in Pressurized Water Reactor Fuel Rod Considering Operational Parameters of the Core	2
Estimation of Densities of Aqueous Actinide Solutions Ranging from Pure Water to Hydrated Crystals	2
The MOOSE Multiphysics Computational Framework for Nuclear Power Applications: A Special Issue of Nuclear Technology	2
Irregular, Backward-Compatible PWR Assembles with More Pins to Facilitate Uprates	2
The Origins of Blast-Loaded Vessels	2
Investigating the Impact of UV-C Radiation on the Mechanical Characteristics of Semifinished Potato Tubers Prepared from Varied Potato Cultivars	2
Enhancement of Fast Neutron Detection in Liquid Scintillator Detectors	2
Initial Studies of Tellurium Embrittlement in 316H Stainless Steel	2
Treatment of Simulated Radioactive Wastewater Using Reverse Osmosis and Membrane Distillation	2
Direct Numerical Simulation of Low and Unitary Prandtl Number Fluids in Reactor Downcomer Geometry	2
Application of Systems Usability Case in an Integrated System Validation of Control Room	2
Measurement of Aerosol Transmission Through a Stress Corrosion Crack–Like Geometry	2
Foreword: Selected papers from the 2021 Nuclear and Emerging Technologies for Space Topical Meeting (NETS 2021)	2
Simulation of Readout Electronics for Nuclear Radiation Detector Using MATLAB Program	2
In-Canal Assay of High Specific Activity 60Co at the Advanced Test Reactor	2
A Framework for Event Detection in Nuclear Facilities Using Wireless Sensors and Actors Networks	2
Organic Telluride Formation from Paint Solvents Under Gamma Irradiation	2
Examination of Deep Learning Algorithm for Nuclear Proliferation Risk Modeling	2
Modeling of the P2M Past Fuel Melting Experiments with the Fuel Performance Code FAST-1.0.1	2
Comparative Study of Raman and EPMA Elemental Mapping of an Unirradiated MOX Sample	2
A Blowdown Critical Heat Flux Experimental Vehicle	2
Comparison of Two Methods for Obtaining the Variabilities in a FRAM Model of a Combined Nuclear Facility Project	2
An Experimental and Theoretical Examination of Air Ingress Rates During Small- and Medium-Break Air Ingress Accidents	2
Numerical Simulation of Wall Condensation from a Superheated Steam and Air Mixture in a Vertical Pipe	2
Criticality Experiments with Fast 235U and 239Pu Metal and Hydride Systems During the Manhattan Project	2
Effect of Nb Addition on Corrosion Resistance of U-6Zr Alloys	2
Current Progress on the Development of the Integrated Waste Management Consent-Based Siting Process in the United States	2
Modeling and Optimization of 147 Pm Radioisotope-Powered GaN-Based PIN Junction Betavoltaic Cell	2
CFD Modeling and Analysis of a Heat-Generating Melt Pool Under External Vessel Cooling and Top Flooding	2