OOIR: Observatory of International Research

Papers

(The median citation count of Nuclear Science and Engineering 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 2021-09-01 to 2025-09-01.)

Article	Citations
Stability and Performance of the X-CMFD Method for Multiphysics Reactor Calculations	82
Uncertainty Quantification of ²³⁷ Np, ²⁴¹ Am, and ²⁴³ Am Reaction Rates in Highly Enriched Uran	21
The Effects of Curved Gas-Liquid Interface on Light Reflectance Liquid Film Measurement for an Optical Waveguide Film	19
Numerical Simulations of Passive Heat Removal from Mobile Microreactors	15
LQG/LTR Controller Design for Power Control of Small Pressurized Water Reactors Under Four Feedback-Controlled Strategies	14
A New Calculation Method Using Pathlines for Delayed Neutron Precursors in Liquid Nuclear Fuels	14
Advances in Nuclear Data and Software Development for the HighNESS Project	13
High-Order Accurate Solutions of the Point Kinetics Equations with the Spectral Deferred Correction Method	13
Analysis of Major Benchmark Uncertainties for Fast Metal Assemblies in the ICSBEP Handbook	12
OpenFOAM-Hybrid: A Morphology Adaptive Multifield Two-Fluid Model	12
Proposed Enhancements to the Risk-Informed and Performance-Based Regulatory Framework for Seismic Hazard Design at NRC-Regulated Nuclear Power Plants	11
Decay Dose Shielding Analysis with Hybrid Unstructured Mesh/Constructive Solid Geometry Monte Carlo Calculation and ADVANTG Acceleration	11
The NILO-CMFD Method for Iteratively Solving Coupled Neutron Transport–Thermal Hydraulics Problems	11
Kinetic Theory Study of Pressure and Equation of State in a Strongly Degenerate Fermi Gas	10
In Situ Electronic Structure Analysis of Water-Corroded UN _x in High Vacuum	10
A Stochastic Calculus Approach to Boltzmann Transport	10
Analysis of Stress Corrosion Cracking Growth Rate in the Heat-Affected Zone of 316L Based on the Heterogeneity of the Mechanical Properties	10
Development of Multigroup Monte Carlo Neutron Transport Method with Regionwise Even-Parity Discontinuity Factor	10
Coupling Fixed-Source Criticality or Criticality and Shielding Modes Within TRIPOLI-4® Monte Carlo Code	10
On the Feasibility of a RGA-Based Decoupling Control in the Reactor-Follow-Turbine Operation of a PWR	10
A New Era of Nuclear Criticality Experiments: The First 10 Years of Flattop Operations at NCERC	9
A Study of the Spatially Developing Laminar-Turbulent Transition in Rod Bundles	9
Extending the Nuclide Inventory Validation Basis for High-Burnup Fuel with New Radiochemical Assay Data	9
MOOSE Reactor Module: An Open-Source Capability for Meshing Nuclear Reactor Geometries	9
A Quasi–Monte Carlo Method With Krylov Linear Solvers for Multigroup Neutron Transport Simulations	8

Multigroup Neutron Transport Using a Collision-Based Hybrid Method	8
Estimating the Impact of an Electromagnetic Pulse Caused by a Hypothetical Surface-Level Nuclear Explosion on Urban Critical Infrastructure	8
Unsupervised Learning for Improved Gamma-Ray Spectrometry in Pixelated Cadmium Zinc Telluride (CZT) Detectors	8
Investigations of Multiphysics Models on a Megawatt-Level Heat Pipe Nuclear Reactor Based on High-Fidelity Approaches	8
Computational Fluid Dynamics Analysis of an Open-Pool Nuclear Research Reactor Core for Fluid Flow Optimization Using a Channel Box	8
Analytic Error Analysis of the Partial Derivatives Cross-Section Model—I: Derivation	8
An Asymptotic-Preserving Hybrid Angular Discretization for the Gray Radiative Transfer Equations	8
Assessment of Modeling Decisions for Depletion Multiphysics Studies of AHTR	7
Multistep Criticality Search and Power Shaping in Nuclear Microreactors with Deep Reinforcement Learning	7
Study on Fission Decay Width of Superheavy Nuclei ²⁹⁸ 119 Synthesized through the Various Fusion Reactions	7
Implementation and Testing of Generalized Perturbation Theory Capabilities in TRIPOLI-4®	7
Statistical Study of Stress and Strain in Matrix of UO ₂ -Zr Plate Type Fuel	7
Reactivity Impact of Updated ³⁵ Cl Nuclear Data on the Molten Chloride Reactor Experiment	7
A New Calculation Strategy for Molten Salt Reactor Neutronic–Thermal-Hydraulic Analysis Implemented with APOLLO3® and TRUST/TrioCFD	7
Probability Density Functions with Correlations of Experimental and Evaluated ²³⁵ U(n _th ,f) Fission Yields and Their Impacts on R	7
Estimation of Near-Field and Far-Field Post-Accident Atmospheric Dispersion for Microreactors	7
Pressurized Water Reactor Core Power Control Using BAS-RBF-PID Approach During Transient Operation	7
Pre-Experimental Assessment of Uranyl Nitrate Solution Irradiation in Kartini Reactor Facilities	7
Variance Reduction and Noise Source Sampling Techniques for Monte Carlo Simulations of Neutron Noise Induced by Mechanical Vibrations	7
The Effect of Branchless Collisions and Population Control on Correlations in Monte Carlo Power Iteration	6
On the Accuracy of Transport Spatial Discretization Methods for Diffusive Regimes	6
Interaction of Cesium Hydroxide with Oxide Layers Under Simulated Light Water Reactor Severe Accident	6
Coupling Nuclear Predictions into Damage Simulations with SPECTRA-PKA	6
Improvements in Antineutrino Spectrum by Including Fission Product Corrections and Calculation of Scatter-Based Pulse Height Distributions	6
Research and Application of the Rehomogenization Method for PWR Core Neutron Physics Simulation	6
Tool Developments in the OpenMC Code: Correlated Sampling and Transient Fission Matrix Approach Coupled to OpenFOAM	6
Analysis of Second Target Station Target Removal Dose Rates	6
Measurements of Droplet Size and Velocity Distributions During Rod Bundle Core Reflood	6
Demonstrating a Quantitative and Systematic Approach to Reducing Excess Conservativism in Nuclear Criticality Safety Analyses	6
Dismantling and Clearance Approach for the Swiss Light Source (SLS)	6
Performance Improvement of Weight Window Method by Incorporating DXTRAN	6
One-Dimensional Drift Flux Analysis of Bubbly Flows in Horizontal and Inclined-Upward Orientations	6
Numerical Investigation of Process Parameter Effects on Flow Oscillations in a Natural Circulation Boiling Integral PWR-Type SMR Test Rig	6
Comparative Analysis of Standard and Advanced USL Methodologies for Nuclear Criticality Safety	6
Development of a TRACE Critical Break LOCA Model for D-PSA Applications with RAVEN	6
Alkaline Hydrolysis of Tri-iso-amyl Phosphate in n-dodecane Using Sodium Hydroxide: Part 1—Factors Affecting the Hydrolysis Process	6
Uncertainty Benchmarks for Time-Dependent Transport Problems	6
Analysis of the Use of Different Backing Layer Materials in the Design of Alpha-Decay Sails for Interplanetary and Interstellar Travel	6
A 2-D Physics Study for Understanding Moderator Temperature Coefficient of Burnable Absorber–Loaded Prismatic High-Temperature Helium-Cooled Reactor	6
Utilizing Sensitivity and Correlation Coefficients from MCNP and Whisper to Guide Microreactor Experiment Design	6
Simulation Analysis Based on Sodium-Cooled Fast Reactor Fuel Assembly Under Blockage Accident	6
Measurements of Neutron Scattering from a Copper Sample Using a Quasi-Differential Method in the Region from 2 keV to 20 MeV	5
A Dynamic Risk Framework for the Physical Security of Nuclear Power Plants	5
Investigations of Suction Recirculation in Primary Sodium Pump of Future Indian Fast Breeder Reactors	5
Effect of Internal Decay Power and Surface Cooling on Nuclear Fuel Droplet Solidification During MFCI in a SFR—A Numerical Study	5
Parallel Simulated Annealing, Genetic Algorithms, and Hybrid Method Applied to the Multiobjective Optimization of the Nuclear In-Core Fuel Management	5
Fuel Cycle Performance of the Wielenga Innovation Static Salt Reactor	5
Developing a Deterministic Calculation Scheme for Perturbations of In-Core Instrumentation of an MTR Core in Support of Bayesian Calibration	5
Impact of the Multigroup Velocity Approximation in the Evaluation of the Effective Neutron Lifetime	5
Lagrangian Investigation of Convective Mass Transfer of Dissolved Elements at Specimen Boundaries in a Flowing Molten Lead Loop	5

Volume Mesh–Based Monte Carlo Particle Transport with Barycentric Particle Tracking	5
Design and Development of the 200-kW Beam Dump	5
Axial Power Distribution Using Improved Axial Reflector Constants Calculation	5
Scoping Analysis of Pebble-Bed Reactors for the Destruction of the Transuranic Inventory of LWR Spent Nuclear Fuel	5
Numerical Simulation of Turbulent Flow and Friction Characteristics Through a Loop of Narrow Rectangular Channel Under Rolling Motions	5
Development of Conceptual Lead Cartridge Design to Perform Irradiation Experiments in VTR	5
The Solitary Wave in Advanced Nuclear Energy System	5
An Analytic Benchmark for Neutron Boltzmann Transport with Downscattering—Part IV: PFNS and ν‾ Uncertainty Propagation	5
Space-Dependent Calculation of the Multiplicity Moments for Shells With the Inclusion of Scattering	5
Uncertainty Analysis of the Reaction Rates in Ringhals	5
Magnetohydrodynamic Analyses of a Miniature, Dual-Stage Electromagnetic Pump for Lead and Sodium In-Pile Test Loops	5
Accelerator Technology for Well Logging: Advances, Challenges, and Opportunities	5
High-Order Perturbation Method for Updating Response Functions for Time-Dependent Transport Calculations	4
Analysis of Corner Balance Nonlinear Diffusion Acceleration and Moment-Based, Spatially Linear Transport Discretizations	4
Void Reactivity in Lead and Bismuth Sample Reactivity Experiments at Kyoto University Critical Assembly	4
Radiation Protection at Petawatt Laser-Driven Accelerator Facilities: The ELI Beamlines Case	4
Simplified Treatment of Coating Layers in TRISO Fuel in Statistical Geometry Method in Monte Carlo Calculation	4
A Parallel Coloring Newton-Krylov Method for Multiphysics Coupling System in Nuclear Reactors	4
Measurements of the Neutron Total and Capture Cross Sections and Derivation of the Resonance Parameters of ¹⁸¹ Ta	4
New Measurements to Resolve Discrepancies in Evaluated Model Parameters of ¹⁸¹ Ta	4
Estimation of ¹³⁷ Cs Contamination Density of Wall, Ceiling, and Floor at Unit 2 Operation Floor in Fukushima Daiichi Nuclear Power Station Using Pinhole Gamma Camer	4
Direct Numerical Simulation of High Prandtl Number Fluid Flow in the Downcomer of an Advanced Reactor	4
On the Uncertainty Analysis of the Data-Enabled Physics-Informed Neural Network for Solving Neutron Diffusion Eigenvalue Problem	4
Post-Neutron Mass Yield Distribution in the Epi-Cadmium Neutron-Induced Fission of ²⁴¹ Pu	4
Accelerating Long-Term Xenon Dynamics Prediction: A Reduced-Order Hybrid Recurrent Neural Network with Intrinsic Physics	4
On the Role of Axial Neutron Flux Mode Excitation in BWR Stability and Nonlinear Oscillations	4
High-Order Finite Element Second Moment Methods for Linear Transport	4
Study on Logging Identification of Sandstone-Type Uranium Deposits Based on Ensemble Learning in the Songliao Basin in Northeast China	4
Exponential Time Differencing Schemes for Fuel Depletion and Transport in Molten Salt Reactors: Theory and Implementation	4
A Study of Gamma Heating, Neutron Flux, and Gamma Flux Under Several Reactor Core Conditions in the McMaster Nuclear Reactor	4
Design and Analyses of Miniature, Submersible Annular Linear Induction Pump for Test Loops Supporting Development of Advanced Nuclear Reactors	4
Preference-Based Multi-Robot Planning for Nuclear Power Plant Online Monitoring and Diagnostics	4
Spherical Harmonics and Discontinuous Galerkin Finite Element Methods for the Three-Dimensional Neutron Transport Equation: Application to Core and Lattice Calculation	4
Analyzing APR1400 System Response Under Load Follow Operation Using a Multiphysics Approach	4
Some Considerations on the Equations Employed to Describe Multiplicity Moments	4
Capability Extension of the High-Resolution Thermal-Hydraulic Code ESCOT for Hexagonal Geometry Core Multiphysics Analysis	4
Generalized Integral Method for Solving the Neutron Transport Equation with the Hybridized Discontinuous Galerkin Method	4
State of the Art in Cyclotrons for Radionuclide Production in Biomedicine	4
Two-Step Monte Carlo Calculation Method for Sensitivity Coefficients of Reactor Period with Respect to Kinetics Parameters	4
A General Formulation of the Resonance Spectrum Expansion Self-Shielding Method	4
Implementation of Resonance Upscattering Treatment in FRENDY Nuclear Data Processing System	4
Selected papers from the 17th International Topical Meeting on Probabilistic Safety Assessment and Analysis (PSA 2021)	4
Safety Analysis in VVER-1000 Due to Large-Break Loss-of-Coolant Accident and Station Blackout Transient Using RELAP5/SCDAPSIM/MOD3.5	4
DOE Robot Perspective: Past, Present, and Future	4
Data-Enabled Physics-Informed Machine Learning for Reduced-Order Modeling Digital Twin: Application to Nuclear Reactor Physics	4
Resolved Resonance Evaluation for Neutron Interactions with ¹⁰³ Rh up to 8 keV	4
Reactor Physics Monitoring of a Source-Driven Subcritical System in Stationary State by Deterministic and Probabilistic Deep Neural Networks	4
A Study of Nuclear Fuel Burnup Wave Development in a Fast Neutron Energy Spectrum Multiplying Medium: Improved Model and Consistent Parametric Approach for Evaluation	3
Experimental Analyses of Capture Reaction Rates for Epithermal and Resonance Neutrons in Source-Driven Subcritical Cores	3
Quantification and Propagation of Uncertainties in R-Matrix Limited Resonance Parameters	3
Bayesian Estimation of Cross Section, Experimental Error, and Calculation Error: Comparison with Bias Factor Method	3
Effect of Backing on Neutron Spectra for Low-Energy Quasi-Monoenergetic p + ⁷ Li Reaction	3
Recent Advances in the Fenton Process for Treatment and Volume Reduction of Liquid Radioactive Waste	3
Identification of Important Phenomena for Light Water Reactors During Heat Transport System Failure Events in Integrated Energy Systems	3
Optimizations of the Accelerated Axial Polynomial Method of Characteristics of the APOLLO3® Deterministic Neutron Transport Code	3
Development and Validation of Thermal-Mechanical Creep Failure Module for Reactor Pressure Vessel Lower Head	3
Application of Accelerator Beam Dumps for Dark Matter Searches	3
Investigations of Gamma and Neutron Shielding Parameters of Ti-Nb-Fe-Cr Alloys with Varying Cr Concentrations	3
Neutron Noise Measurements of a Fast HEU Copper System	3
Convergence Properties of a Linear Diffusion-Acceleration Method for k-Eigenvalue Transport Problems	3
On MCNP Stochastic Volume Estimation Normalization	3
Preparation and Electrical Performance Analysis of a GaAs‐Based Tritium Battery	3
An Experimental Investigation of Two-Phase Frictional Pressure Drop in Straight-Tube Steam Generator Used in SFR	3
A Residual-Based Subgrid-Scale Method Combined with Spherical Harmonics Angular Approximation for Solving the Boltzmann Transport Equation	3
Activation Analysis in Preparation for a Tungsten Irradiation Experiment at LANSCE	3
A Consistent Low-Order Acceleration Technique for Coarse Mesh Transport (COMET) Methods	3
A Consequence-Informed Licensing Path Selection for the Design of Physical Protection Systems at Commercial Nuclear Power Facilities	3
Designing the Second Target Station with a Coupled Neutronics-Mechanical Optimization Workflow	3
Morphological Characterization of Uranyl Fluoride Particles via Atomic Force Microscopy	3
Evaluating Quantities of Interest Other Than Nuclide Densities in the Bateman Equations	3
Ionization Efficiency Measurement and Optimization of a Thermal Ion Source for Radioisotope Electromagnetic Separation	3
Applicability of Dynamic Mode Decomposition to Estimate Fundamental Mode Component of Prompt Neutron Decay Constant from Experimental Data	3
Stress Profile in Coating Layers of TRISO Fuel Particles in Contact with One Another	3
A Unified Framework of Stabilized Finite Element Methods for Solving the Boltzmann Transport Equation	3
An Iterative RSA-DEM Method for High Particle Packing Fraction Stochastic Media	3
Computationally Optimized Irradiation Chamber Design for Production of ¹³⁵ Xe in the Washington State University TRIGA Reactor	3
Application of MELCOR for Simulating Molten Salt Reactor Accident Source Terms	3
First Order Response Matrix Benchmark for the 1D Transport Equation with Matrix Scaling	3
Comparison of ²³⁸ U and ²³⁵ U Fission Chambers for Monitoring the Reactivity of the VENUS-F Accelerator-Driven Subcritical Reactor	3
A Pragmatic Approach to Update Support Studies and Human Reliability Analyses for a PSA Model	3

Linear Source Approximation in MPACT for Efficient and Robust Multiphysics Whole-Core Simulations	3
Development of a Coupled Depletion Perturbation Theory Methodology in Continuous-Energy Monte Carlo Depletion Simulations	3
Integrated Safety and Security Analysis of Nuclear Power Plants Using Dynamic Event Trees	3
Optimizing Hydride Stability in U-ZrH _x Nuclear Fuel: The “Goldilocks Radius”	3
Comparing Coupled Multiphysics Simulations of Pump-Driven Transients for a Pressurized Heavy Water Reactor	3
Moment Asymptotics for the Neutron Transport Equation	3
Preliminary Neutronics Design and Analysis of the Fast Modular Reactor	3
Feasibility of Photonuclear Transmutation of Long-Lived Fission Products Extracted from Used Nuclear Fuel	3
An Improved Dual Asymmetric Penalized Least Squares Baseline Correction Method for High-Noise Spectral Data Analysis	3
COAL Experiments Investigating the Reflooding of a 7 × 7 Rod Bundle During a Loss-of-Coolant Accident: Effect of a Partially Blocked Area with Ballooned Rods	3
Physics-Informed Neural Networks for 1-D Steady-State Diffusion-Advection-Reaction Equations	3
Influence of Quantum Oscillations in the Thermal Scattering Law of Zirconium Carbide on Neutron Thermalization and Criticality	3
A Method to Calculate the Maturity Time for Low Neutron Source Nuclear Reactor Startup Simulations	3
Development, Verification, and Validation of an Advanced Systems Code KP-SAM for Kairos Power Fluoride Salt–Cooled High-Temperature Reactor (KP-FHR)	3
An Attention-Based CNN-LSTM Model to Diagnose Break Size in Loss-of-Coolant Accidents	3
Combining Similarity Measures and Left-Right Hidden Markov Models for Prognostics of Items Subjected to Perfect and Imperfect Maintenance	3
Technical Reviewers	2
Scoping Studies for a Lead-Lithium-Cooled, Minor-Actinide-Burning, Fission-Fusion Hybrid Reactor Design	2
Blind Benchmark Exercise for Spent Nuclear Fuel Decay Heat	2
Few-View CT Image Reconstruction via Least-Squares Methods: Assessment and Optimization	2
Research on Nuclear Power Plant Operational Task Complexity Assessment Method Based on Group Decision Making and Deep Learning of EEG Signals	2
Dynamic Modeling of a Fast Spectrum Molten Salt Reactor Integrated Energy System	2
Optimization of Personnel Work Paths During Decommissioning of Nuclear Facilities	2
FLASSH 1.0: Thermal Scattering Law Evaluation and Cross-Section Generation for Reactor Physics Applications	2
Early-Stage Radiation Safety Analysis for the Spallation Neutron Source Second Target Station Bunker Operations	2
Establishment of Control Room Habitability Analysis Methodology Postulating the Event of Pressurized Tank/System of Hazardous Gas Release	2
ADDENDUM: Validation of Continuous-Energy ENDF/B-VIII.0 ¹⁶O, ⁵⁶Fe, and ^63,65Cu Cross Sections for Nuclear Criticality Safety Applications	2
Charge Distribution Studies in the Epi-Cadmium Neutron-Induced Fission of ²⁴¹ Pu	2
The Versatile Test Reactor Project: Mission, Requirements, and Description	2
Post-Neutron Mass Yield Distribution in the Epi-Cadmium Neutron-Induced Fission of²⁴⁵Cm	2
Assessment of JEFF Nuclear Data Libraries for Reactor Physics and Spent Fuel Composition Applications	2
Continuous-Energy ENDF/B-VIII.0 Cross Section and SCALE 6.2.4 Performance for Nuclear Criticality Safety Applications: ¹H, C, ^58,60Ni, ^{182,183,184,186}W, ^235,238	2
Statistical Methods for the Study of Computer Experiment Failures: Application to a Fuel-Coolant-Interaction Simulation Code	2
CFD Simulation of Melt Pool Coolability in a Simulated Core Catcher Model	2
Current State of the Design Engineering of the Versatile Test Reactor Plant	2
Welch Method and Bootstrapping Applied to Subcritical Gamma Noise	2
Monte Carlo Calculation Method for Reactor Period Utilizing the Differential Operator Sampling Technique	2
Nonconforming Three-Dimensional Model for PWR Control Rod Movements Without Homogenization and Cusping Effect	2
On the Assumptions Behind Statistical Sampling: A ²³⁵ U Fission Yield Uncertainty Propagation Case Study	2
Hybrid Variable Selection for Estimating Nominal HEPs and PIF Multipliers for Digital Control Rooms	2
Effects of Cold Rolling–Induced Defects on Proton Irradiation Response in Nb-1Zr-0.1C Alloy	2
Impact Assessment of Radiative Heat Transport in ARC-Class Reactor FLiBe Liquid Immersion Blanket	2
Measurement of the Prompt Neutron Decay Constant in a Zero-Power Reactor Using a Novel 3D Detector System	2
Thermodynamic Assessment of the NaCl-CrCl ₂ , NaCl-CrCl ₃ , and FeCl ₂ -CrCl ₂	2
Locational Variance in Nuclear Microreactor Performance Under Net Zero Microgrid Conditions	2
Flow-Induced Vibrations of Two Flexible Tubes in Cross Flow	2
Special issue featuring papers from the 2023 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2023) Guest Editors	2
A Novel ERANOS Procedure for Sensitivity Analyses in Core Depletion Problems: Implementation Details and Verification	2
Advanced High-Temperature Sodium-Cooled Thermal Reactors Using Less Than 10% Enriched UO ₂ Fuel	2
Preconceptual Design of Multifunctional Gas-Cooled Cartridge Loop for the Versatile Test Reactor: Instrumentation and Measurement—Part II	2
MaCaw: Domain-Decomposed Monte Carlo Neutral Particle Transport on Unstructured Mesh in MOOSE	2
Numerical Investigation on the Thermal-Hydraulic Characteristics near a Corroded Lower Head of the Reactor Vessel During IVR-ERVC	2
Thermal-Hydraulic Investigation of Steady-State Single-Phase Natural Circulation of an Integral PWR-Type SMR Test Rig (iPSTR)	2
A Novel High-Order Surface Characteristics Scheme for the Neutron Transport Equation in 2D Unstructured Meshes	2
Study on Photon Beam Imaging Properties of CsPbBr ₃ -PP Scintillator: Monte Carlo Simulation Approach	2
Improvements to the Baff-Refl Equivalence Technique Applied to Reflector Models in PWRs	2
CANDU Station Blackout D-PSA with RAVEN and TRACE Software	2
Challenges and Technology-Driven Opportunities for Safeguarding Microreactors	2
Real-Time State Estimation of Neutron Flux in Molten Salt Fast Reactors from Out-Core Sparse Measurements	2
Nondestructive Measurement Method of Nuclear Materials for Sorting Nuclear Fuel Debris	2
Using a Random Forest Model to Choose Optimized Group Structures	2
Core Reload Design Using Genetic Optimization for Cost Savings in a Two-Reactor Power Plant With Used Fuel Sharing	2
Informing Performance Metrics of Advanced I&C Systems for Liquid Fueled Fast Molten Salt Reactors	2
CFD Investigations to Understand Thermal Performance of Helically Rifled Heat Transfer Enhancements in Molten Salt Applications	2
Gas-Liquid Two-Phase Flow Regime in a Horizontal Channel Under Transverse Vibration	2
Low-Temperature MOCVD Deposition of Vanadium Carbide on F/M Steel for Mitigating Fuel-Cladding Chemical Interaction	2
Two-Phase Turbulent Kinetic Energy Budget Computation in Co-Current Taylor Bubble Flow	2
Three-Dimensional Thermal Modeling of In Situ Heating Tests for High-Level Radioactive Nuclear Waste Repository	2
Development of Uncertainty Analysis Techniques for the Fission Matrix–Based Neutron Transport Code RAPID	2
Derivation of Uncertainty Distributions for Channel Flow Rate and Fuel Critical Heat Flux Predictions for Best-Estimate Plus Uncertainty Analysis of Slow Loss-of–Reactor Power Regulation Accidents in	2
Radiolytic Production of Fluorine Gas from MSR Relevant Fluoride Salts	2
Effects of Temperature and Electron Energy on the Defect Evolution Behavior of Pristine and Ion-Irradiated Yttria-Stabilized Zirconia	2
Demonstration of TOFFEE: A Response Uncertainty Quantification Tool	2
A Path Planning Algorithm Considering the Feasibility Region of Nuclear Decommissioning Robots	2
Numerical Investigation of Air-Steam Condensation in a Vertically Enhanced Tube with Concave and Convex Surfaces	2
Experimental Estimation of the Kinetic Parameters of MINERVE Zero Power Reactor	2
A Benchmark for Neutron Kinetics Methods in Hexagonal Geometry	2
On the Numerical Method for Photofission-Based Nuclear Material Isotopic Composition Estimation in Thorium-Uranium Systems	2
A Practical Comparison of Data-Driven Prognostics Methods for Energy Systems	2
Advanced Liquid-Metal-Cooled Fast Reactor Core Design Using Modern Optimization Algorithms	2
Real-Time Monitoring for Detection of Adversarial Subtle Process Variations	1
A Nonintrusive Nuclear Data Uncertainty Propagation Study for the ARC Fusion Reactor Design	1
Convergence Study of 2D Transport Method for Multigroup k-Eigenvalue Problems with High-Order Scattering Source Using Fourier Analysis	1
Computational Investigation of Optimal Discharge Header Design in a Typical Open Pool–Type Research Reactor for Flow Stability in Hot Water Layer System	1
Stochastic Optimization to Find Optimum Beginning-of-Life Core Configuration of Stable Salt Reactor with Online Refueling	1
Examining Beam Matching in the Commissioning of a Halcyon Accelerator	1
Modeling and Simulation of Radioactive Nanomaterials of Pb-U, Pb-Th, and Pb-Co in Water-Filled Containers for Nuclear Security Applications	1
Parametric Model-Order Reduction for Radiation Transport Simulations Based on an Affine Decomposition of the Operators	1
Development of a 3D APOLLO3® Neutron Deterministic Calculation Scheme for the CABRI Experimental Reactor	1
Uncertainty Quantification Framework for High-Temperature Gas-Cooled Reactors Using VSOP and DAKOTA	1
Scaling, Passive Systems, and the AP-1000	1
Study on LOFA and LOHS Accidents with Passive Safety System for Integrated Marine Reactor	1
A High-Throughput Hot Surface Ion Source for Electromagnetic Radioisotope Separation	1
SCALE Shielding Calculations for Advanced Reactor Accident Scenarios	1
Mass Optimization of a Multilayered Shield for Transportable Microreactors	1