Nuclear Science and Engineering

Article	Citations
Stability and Performance of the X-CMFD Method for Multiphysics Reactor Calculations	37
High-Order Accurate Solutions of the Point Kinetics Equations with the Spectral Deferred Correction Method	30
Advances in Nuclear Data and Software Development for the HighNESS Project	27
Uncertainty Quantification of 237 Np, 241 Am, and 243 Am Reaction Rates in Highly Enriched Uran	25
Advancing the STS Neutron Moderator Design with an Automated Optimization Workflow and Unstructured Mesh Modeling	24
Decay Dose Shielding Analysis with Hybrid Unstructured Mesh/Constructive Solid Geometry Monte Carlo Calculation and ADVANTG Acceleration	20
The NILO-CMFD Method for Iteratively Solving Coupled Neutron Transport–Thermal Hydraulics Problems	19
Kinetic Theory Study of Pressure and Equation of State in a Strongly Degenerate Fermi Gas	18
Proposed Enhancements to the Risk-Informed and Performance-Based Regulatory Framework for Seismic Hazard Design at NRC-Regulated Nuclear Power Plants	16
Radiation-Hardened DC-DC Converter Design: Systematic Analysis of Single-Event Transient Effects and Voltage Clamping Mitigation Strategy	16
On the Feasibility of a RGA-Based Decoupling Control in the Reactor-Follow-Turbine Operation of a PWR	16
Coupling Fixed-Source Criticality or Criticality and Shielding Modes Within TRIPOLI-4® Monte Carlo Code	16
A Stochastic Calculus Approach to Boltzmann Transport	15
Bubble Dynamics in a Subcooled Boiling Flow at a High Pressure	15
Predicted DBA Doses Versus Fukushima Accident Doses: A Comparative Analysis	15
LQG/LTR Controller Design for Power Control of Small Pressurized Water Reactors Under Four Feedback-Controlled Strategies	13
A New Calculation Method Using Pathlines for Delayed Neutron Precursors in Liquid Nuclear Fuels	12
Numerical Simulations of Passive Heat Removal from Mobile Microreactors	12
Development of Multigroup Monte Carlo Neutron Transport Method with Regionwise Even-Parity Discontinuity Factor	12
Application of CASMO5 to Similarity Analysis Using Integral Indices	12
MOOSE Reactor Module: An Open-Source Capability for Meshing Nuclear Reactor Geometries	12
OpenFOAM-Hybrid: A Morphology Adaptive Multifield Two-Fluid Model	12
Graph Theory and Spectral Effects in CRAM and BDF Solutions of the Nuclear Inventory Equation	12
Adjoint-Based Surrogate Modeling of Detector Responses for Repositioned Volumetric Sources	11
The Effects of Curved Gas-Liquid Interface on Light Reflectance Liquid Film Measurement for an Optical Waveguide Film	11

Analysis of Major Benchmark Uncertainties for Fast Metal Assemblies in the ICSBEP Handbook	11
Extending the Nuclide Inventory Validation Basis for High-Burnup Fuel with New Radiochemical Assay Data	11
Analysis of Stress Corrosion Cracking Growth Rate in the Heat-Affected Zone of 316L Based on the Heterogeneity of the Mechanical Properties	11
In Situ Electronic Structure Analysis of Water-Corroded UN x in High Vacuum	10
Quantifying the Effect of Material Aging on the Performance and Reliability of Passive Heat Removal Systems in Liquid Metal Fast Cooled Reactors	10
Nuclear Electric Propulsion for Deep-Space Missions: Technologies, Challenges, and Future Outlook	10
A Study of the Spatially Developing Laminar-Turbulent Transition in Rod Bundles	10
Thickness Assessment for Accident-Tolerant FeCrAl Fuel Cladding Based on Elastoplastic and Creep Buckling Analyses	9
MAVOR—A Tool to Create Fully Continuous, Linearized, Temperature On-the-Fly Thermal Neutron Sampling Distributions	9
Human Reliability Dependency Assessment in Beyond Design-Basis Accidents: Extending the EMBRACE Dependency Equation	9
Computational Fluid Dynamics Analysis of an Open-Pool Nuclear Research Reactor Core for Fluid Flow Optimization Using a Channel Box	9
Expert Insights into Challenges in the Probabilistic Risk Assessment for Advanced Nuclear Power Technologies	9
Analytic Error Analysis of the Partial Derivatives Cross-Section Model—I: Derivation	8
Revisiting Mark’s Two-Region Problem in Spherical Geometry	8
Monte Carlo and Deterministic Implementations of the Zeta-Eigenvalue Equation for Efficient Criticality Searches	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
Statistical Study of Stress and Strain in Matrix of UO 2 -Zr Plate Type Fuel	8
Investigations of Multiphysics Models on a Megawatt-Level Heat Pipe Nuclear Reactor Based on High-Fidelity Approaches	8
An Asymptotic-Preserving Hybrid Angular Discretization for the Gray Radiative Transfer Equations	8
Feature Selection Approaches for Gamma Spectroscopy and Weapons-Grade Plutonium Classification	8
Multigroup Neutron Transport Using a Collision-Based Hybrid Method	8
Estimation of Near-Field and Far-Field Post-Accident Atmospheric Dispersion for Microreactors	8
Pre-Experimental Assessment of Uranyl Nitrate Solution Irradiation in Kartini Reactor Facilities	7
One-Dimensional Drift Flux Analysis of Bubbly Flows in Horizontal and Inclined-Upward Orientations	7
Ants and DYN3D Solutions to the IAEA-Hex Kinetics Benchmark	7
A Quasi–Monte Carlo Method With Krylov Linear Solvers for Multigroup Neutron Transport Simulations	7
Implementation and Testing of Generalized Perturbation Theory Capabilities in TRIPOLI-4®	7
Research and Application of the Rehomogenization Method for PWR Core Neutron Physics Simulation	7
Tool Developments in the OpenMC Code: Correlated Sampling and Transient Fission Matrix Approach Coupled to OpenFOAM	7
Multistep Criticality Search and Power Shaping in Nuclear Microreactors with Deep Reinforcement Learning	7
The Effect of Branchless Collisions and Population Control on Correlations in Monte Carlo Power Iteration	7
Development of a TRACE Critical Break LOCA Model for D-PSA Applications with RAVEN	7
Comparative Analysis of Standard and Advanced USL Methodologies for Nuclear Criticality Safety	7
Analysis of Second Target Station Target Removal Dose Rates	7
Environment Insensitive Reflector Homogenization Through a Response Matrix Equivalence Method Based on the Relaxed Flux Continuity Equation	7
Probability Density Functions with Correlations of Experimental and Evaluated 235 U(n th ,f) Fission Yields and Their Impacts on R	7
Pressurized Water Reactor Core Power Control Using BAS-RBF-PID Approach During Transient Operation	7
Numerical Investigation of Process Parameter Effects on Flow Oscillations in a Natural Circulation Boiling Integral PWR-Type SMR Test Rig	7
A Methodology for Estimating the Ensemble-Averaged Effective Multiplication Factor and Neutron Scalar Flux Profile in Statistically Homogeneous Random Media Using a Slab-Geometry, Discrete Ordinates a	7
Study on Fission Decay Width of Superheavy Nuclei 298 119 Synthesized Through the Various Fusion Reactions	7
Reactivity Impact of Updated 35 Cl Nuclear Data on the Molten Chloride Reactor Experiment	7
Calculation of Adjoint-Weighted Kinetics Parameters in OpenMC Using the Iterated Fission Probability Method	6
Utilizing Sensitivity and Correlation Coefficients from MCNP and Whisper to Guide Microreactor Experiment Design	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
Analysis of the Use of Different Backing Layer Materials in the Design of Alpha-Decay Sails for Interplanetary and Interstellar Travel	6
Cross-Section Calculations For nat Ir(α,x) Reactions: Effects of Level Density Models and Alpha Optical Model Potential Combinations	6
Mass Yield Distributions in the 13.75-MeV Quasi-Mono-Energetic Neutron-Induced Fission of 232 Th and 238	6
Assessment of the Random Ray Method for Neutron Transport Problems with Strong Angular Anisotropy	6

Variance Reduction and Noise Source Sampling Techniques for Monte Carlo Simulations of Neutron Noise Induced by Mechanical Vibrations	6
Uncertainty Benchmarks for Time-Dependent Transport Problems	6
A New Calculation Strategy for Molten Salt Reactor Neutronic–Thermal-Hydraulic Analysis Implemented with APOLLO3® and TRUST/TrioCFD	6
Development of MOSCATO: A CFD-Level Electrochemistry and Corrosion Simulator for Molten Salt Systems	6
Assessment of Modeling Decisions for Depletion Multiphysics Studies of AHTR	6
Simulation Analysis Based on Sodium-Cooled Fast Reactor Fuel Assembly Under Blockage Accident	6
On the Accuracy of Transport Spatial Discretization Methods for Diffusive Regimes	6
Dismantling and Clearance Approach for the Swiss Light Source (SLS)	6
Computational Optimization of 133m Xe Production via Neutron Irradiation in a TRIGA Reactor	5
A Novel Winglet-Type Arc-Vane Swirler and Its Influence on Spiral Annular Flow	5
State of the Art in Cyclotrons for Radionuclide Production in Biomedicine	5
Magnetohydrodynamic Analyses of a Miniature, Dual-Stage Electromagnetic Pump for Lead and Sodium In-Pile Test Loops	5
Two-Step Monte Carlo Calculation Method for Sensitivity Coefficients of Reactor Period with Respect to Kinetics Parameters	5
Interaction of Cesium Hydroxide with Oxide Layers Under Simulated Light Water Reactor Severe Accident	5
Performance Improvement of Weight Window Method by Incorporating DXTRAN	5
Improvements in Antineutrino Spectrum by Including Fission Product Corrections and Calculation of Scatter-Based Pulse Height Distributions	5
Investigations of Suction Recirculation in Primary Sodium Pump of Future Indian Fast Breeder Reactors	5
Space-Dependent Calculation of the Multiplicity Moments for Shells With the Inclusion of Scattering	5
Production of High-Purity 123 I Radioisotope from Natural and Enriched Tellurium Dioxide Using 122	5
High-Order Perturbation Method for Updating Response Functions for Time-Dependent Transport Calculations	5
Resolved Resonance Evaluation for Neutron Interactions with 103 Rh up to 8 keV	5
Capability Extension of the High-Resolution Thermal-Hydraulic Code ESCOT for Hexagonal Geometry Core Multiphysics Analysis	5
Thermodynamic Assessment of the Na,K,Cs|Cl,I Reciprocal Salt for Chloride-Fueled MSR Accident Analysis	5
A 2-D Physics Study for Understanding Moderator Temperature Coefficient of Burnable Absorber–Loaded Prismatic High-Temperature Helium-Cooled Reactor	5
Coupling Nuclear Predictions into Damage Simulations with SPECTRA-PKA	5
Volume Mesh–Based Monte Carlo Particle Transport with Barycentric Particle Tracking	5
An Analytic Benchmark for Neutron Boltzmann Transport with Downscattering—Part IV: PFNS and ν‾ Uncertainty Propagation	5
A Dynamic Risk Framework for the Physical Security of Nuclear Power Plants	5
High-Temperature Neutron Irradiation of Ni-Based Structural Alloys for Application in Molten Salt Nuclear Reactors	5
Reactor Physics Monitoring of a Source-Driven Subcritical System in Stationary State by Deterministic and Probabilistic Deep Neural Networks	5
Accelerator Technology for Well Logging: Advances, Challenges, and Opportunities	5
Model Predictive Control of a Small Modular Reactor with Partial Steam Diversion to Thermal Energy Storage with RELAP5-3D	5
Numerical Simulation of Turbulent Flow and Friction Characteristics Through a Loop of Narrow Rectangular Channel Under Rolling Motions	5
Alkaline Hydrolysis of Tri-iso-amyl Phosphate in n-dodecane Using Sodium Hydroxide: Part 1—Factors Affecting the Hydrolysis Process	5
Impact of the Multigroup Velocity Approximation in the Evaluation of the Effective Neutron Lifetime	5
Nuclear Forensics: The Ultimate Analytical Chemistry Challenge	5
Spatial Correlations of the Poisson Model for Radiation Transport	5
Special Issue Featuring Papers from the 2024 ANS Radiation Protection and Shielding Division Topical Meeting	5
On the Uncertainty Analysis of the Data-Enabled Physics-Informed Neural Network for Solving Neutron Diffusion Eigenvalue Problem	4
On MCNP Stochastic Volume Estimation Normalization	4
Consistent Method for Calculating Directional Diffusion Coefficients Using Monte Carlo	4
Characterization of a 6-kg Neptunium Metal Sphere	4
Void Reactivity in Lead and Bismuth Sample Reactivity Experiments at Kyoto University Critical Assembly	4
Development of GPU-Accelerated CMFD for STREAM3D-GPU Neutron Transport Code	4
Post-Neutron Mass Yield Distribution in the Epi-Cadmium Neutron-Induced Fission of 241 Pu	4
Verification and Research of SGTR Accident Based on the PKL Test Facility	4
Axial Power Distribution Using Improved Axial Reflector Constants Calculation	4
Scoping Analysis of Pebble-Bed Reactors for the Destruction of the Transuranic Inventory of LWR Spent Nuclear Fuel	4
Fuel Cycle Performance of the Wielenga Innovation Static Salt Reactor	4
Evaluation of PBR Spent Fuel Criticality and Dose Rate Compliance for Storage and Transportation	4
Generalized Integral Method for Solving the Neutron Transport Equation with the Hybridized Discontinuous Galerkin Method	4
Selected papers from the 17th International Topical Meeting on Probabilistic Safety Assessment and Analysis (PSA 2021)	4
Temperature Limit of Measurement for Perovskite-Type Electrode Oxygen Sensors in Liquid LBE	4
Offline Maximizing Minimally Invasive Proper Orthogonal Decomposition for Reduced-Order Modeling of S n	4
Developing a Deterministic Calculation Scheme for Perturbations of In-Core Instrumentation of an MTR Core in Support of Bayesian Calibration	4
On the Role of Axial Neutron Flux Mode Excitation in BWR Stability and Nonlinear Oscillations	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
Design and Development of the 200-kW Beam Dump	4
Development of New GPU-Optimized Reactor Physics Monte Carlo Code GREAPMC	4
Accelerating Long-Term Xenon Dynamics Prediction: A Reduced-Order Hybrid Recurrent Neural Network with Intrinsic Physics	4
An S 2 Nonlinear Acceleration Scheme for Particle Transport Calculations	4
A General Formulation of the Resonance Spectrum Expansion Self-Shielding Method	4
Development, Verification, and Validation of an Advanced Systems Code KP-SAM for Kairos Power Fluoride Salt–Cooled High-Temperature Reactor (KP-FHR)	4
Measurements of the Neutron Total and Capture Cross Sections and Derivation of the Resonance Parameters of 181 Ta	4
Direct Numerical Simulation of High Prandtl Number Fluid Flow in the Downcomer of an Advanced Reactor	4
First Order Response Matrix Benchmark for the 1D Transport Equation with Matrix Scaling	4
Effect of Internal Decay Power and Surface Cooling on Nuclear Fuel Droplet Solidification During MFCI in a SFR—A Numerical Study	4
Some Considerations on the Equations Employed to Describe Multiplicity Moments	4
Computing the Time-Averaged Nuclide Inventory Using the Chebyshev Rational Approximation Method	4
Parallel Simulated Annealing, Genetic Algorithms, and Hybrid Method Applied to the Multiobjective Optimization of the Nuclear In-Core Fuel Management	4
Spherical Harmonics and Discontinuous Galerkin Finite Element Methods for the Three-Dimensional Neutron Transport Equation: Application to Core and Lattice Calculation	4
Direct Sampling of the Egelstaff-Schofield Scattering Law and the Phonon Sampling Method for Liquids	4
Uncertainty Analysis of the Reaction Rates in Ringhals	4
Bayesian Estimation of Cross Section, Experimental Error, and Calculation Error: Comparison with Bias Factor Method	3
Development and Validation of Thermal-Mechanical Creep Failure Module for Reactor Pressure Vessel Lower Head	3
Stability Analysis of Xenon Oscillation in PHWRs Using Modal Synthesis and Improved Quasi-Static Method: A Comparative Study	3
An Attention-Based CNN-LSTM Model to Diagnose Break Size in Loss-of-Coolant Accidents	3
Prismatic and Pebble-Bed Micro-HTGRs in Continuous-Recycle Nuclear Fuel Cycles	3
Optimizing Hydride Stability in U-ZrH x Nuclear Fuel: The “Goldilocks Radius”	3
Comparison of 238 U and 235 U Fission Chambers for Monitoring the Reactivity of the VENUS-F Accele	3

Stress Profile in Coating Layers of TRISO Fuel Particles in Contact with One Another	3
Importance Sampling for Monte Carlo Dynamic Event Tree Analysis of Accident Scenarios in New-Generation Nuclear Power Plants	3
Application of Accelerator Beam Dumps for Dark Matter Searches	3
Selection-Driven Evolutionary Population Control for Kinetic Monte Carlo Variance Reduction	3
Design and Analyses of Miniature, Submersible Annular Linear Induction Pump for Test Loops Supporting Development of Advanced Nuclear Reactors	3
Radiation Protection at Petawatt Laser-Driven Accelerator Facilities: The ELI Beamlines Case	3
Evaluating Quantities of Interest Other Than Nuclide Densities in the Bateman Equations	3
A Study on the Influence Mechanism of Cognitive Style on Situation Awareness of Nuclear Power Plant Operators	3
Radiation Shielding Properties of Polyethylene Reinforced with PbO and CdO: Experimental and Theoretical Study	3
Preliminary Neutronics Design and Analysis of the Fast Modular Reactor	3
Preference-Based Multi-Robot Planning for Nuclear Power Plant Online Monitoring and Diagnostics	3
Radiation Shielding Analysis of Linac Extension Area in APS Using FLUKA and PHITS Monte Carlo Radiation Transport Codes	3
Simplified Treatment of Coating Layers in TRISO Fuel in Statistical Geometry Method in Monte Carlo Calculation	3
Designing the Second Target Station with a Coupled Neutronics-Mechanical Optimization Workflow	3
Activation Analysis in Preparation for a Tungsten Irradiation Experiment at LANSCE	3
Investigations of Gamma and Neutron Shielding Parameters of Ti-Nb-Fe-Cr Alloys with Varying Cr Concentrations	3
Study on the Automated Welding Process Parameters of the Maintenance Robot for Sheath of Electric Heating Tubes in Pressurizers of Nuclear Power Plant	3
Identification of Important Phenomena for Light Water Reactors During Heat Transport System Failure Events in Integrated Energy Systems	3
Methodologies and Shielding Analysis for the Design of Activated Cooling Water Components in Spallation Neutron Systems	3
Ionization Efficiency Measurement and Optimization of a Thermal Ion Source for Radioisotope Electromagnetic Separation	3
Effect of Backing on Neutron Spectra for Low-Energy Quasi-Monoenergetic p +  7 Li Reaction	3
Development of a Coupled Depletion Perturbation Theory Methodology in Continuous-Energy Monte Carlo Depletion Simulations	3
An Iterative RSA-DEM Method for High Particle Packing Fraction Stochastic Media	3
A Consequence-Informed Licensing Path Selection for the Design of Physical Protection Systems at Commercial Nuclear Power Facilities	3
High-Order Finite Element Second Moment Methods for Linear Transport	3
Convergence Properties of a Linear Diffusion-Acceleration Method for k-Eigenvalue Transport Problems	3
Assessment of JEFF Nuclear Data Libraries for Reactor Physics and Spent Fuel Composition Applications	3
Application of MELCOR for Simulating Molten Salt Reactor Accident Source Terms	3
Linear Source Approximation in MPACT for Efficient and Robust Multiphysics Whole-Core Simulations	3
Study on Logging Identification of Sandstone-Type Uranium Deposits Based on Ensemble Learning in the Songliao Basin in Northeast China	3
Radiolytic Production of Fluorine Gas from MSR Relevant Fluoride Salts	3
New Measurements to Resolve Discrepancies in Evaluated Model Parameters of 181 Ta	3
Comparing Coupled Multiphysics Simulations of Pump-Driven Transients for a Pressurized Heavy Water Reactor	3
Preparation and Electrical Performance Analysis of a GaAs‐Based Tritium Battery	3
A Method to Calculate the Maturity Time for Low Neutron Source Nuclear Reactor Startup Simulations	3
Moment Asymptotics for the Neutron Transport Equation	3
Optimizations of the Accelerated Axial Polynomial Method of Characteristics of the APOLLO3® Deterministic Neutron Transport Code	3
Feasibility of Photonuclear Transmutation of Long-Lived Fission Products Extracted from Used Nuclear Fuel	3
A Pragmatic Approach to Update Support Studies and Human Reliability Analyses for a PSA Model	3
Integrated Safety and Security Analysis of Nuclear Power Plants Using Dynamic Event Trees	3
Morphological Characterization of Uranyl Fluoride Particles via Atomic Force Microscopy	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
Fourier Analysis on the Symmetric Group for a Repositioning Plan Optimization Problem	3
Influence of Quantum Oscillations in the Thermal Scattering Law of Zirconium Carbide on Neutron Thermalization and Criticality	3
An Experimental Investigation of Two-Phase Frictional Pressure Drop in Straight-Tube Steam Generator Used in SFR	3
A Parallel Coloring Newton-Krylov Method for Multiphysics Coupling System in Nuclear Reactors	3
Bounded Newton–Krylov Method for Chemistry-Flow–Heat Transfer Coupling Problem in High Temperature Gas-Cooled Reactors	3
DOE Robot Perspective: Past, Present, and Future	3
Experimental Analyses of Capture Reaction Rates for Epithermal and Resonance Neutrons in Source-Driven Subcritical Cores	3
A Unified Framework of Stabilized Finite Element Methods for Solving the Boltzmann Transport Equation	3
A Sector Ring Model for Nuclear Radiation Environment Representation and Hazard Avoidance	3
Neutron Noise Measurements of a Fast HEU Copper System	3
Preliminary Verification of Fixed-Source Sensitivity Analysis in OpenMC	3
Multi-Objective Optimization of Uranium Target Assembly–3: A Comparison of Genetic and Traditional Methods	3
Quantification and Propagation of Uncertainties in R-Matrix Limited Resonance Parameters	3
A Consistent Low-Order Acceleration Technique for Coarse Mesh Transport (COMET) Methods	3
Interplay of Variance Reduction and Population Control in Monte Carlo Neutron Transport	3
Current Status of TRIPOLI-4® Monte Carlo Radiation Transport Code on Adult and Pediatric Computational Phantoms for Radiation Dosimetry Study	2
Analysis of Integral Experiment of the AHWR Critical Facility with Diffusion-Based Monte Carlo Method	2
Measurement of the Prompt Neutron Decay Constant in a Zero-Power Reactor Using a Novel 3D Detector System	2
Three-Dimensional Thermal Modeling of In Situ Heating Tests for High-Level Radioactive Nuclear Waste Repository	2
Post-Neutron Mass Yield Distribution in the Epi-Cadmium Neutron-Induced Fission of 245 Cm	2
Low-Temperature MOCVD Deposition of Vanadium Carbide on F/M Steel for Mitigating Fuel-Cladding Chemical Interaction	2
Study on Photon Beam Imaging Properties of CsPbBr 3 -PP Scintillator: Monte Carlo Simulation Approach	2
On the Isotropic Approximation for Angular Flux Time Derivatives in Modeling Reactor Transients	2
Informing Performance Metrics of Advanced I&C Systems for Liquid Fueled Fast Molten Salt Reactors	2
A Comment on a Streaming Operator that Preserves Spherical Symmetry in Cylindrical Coordinates	2
Development of HELIOS/BIPR/PARCS/MCNP6 Computation Route for WWER RPV Neutron Fluence Analysis and Validation Against Ex-Vessel Detector Measurement Data	2
Nondestructive Measurement Method of Nuclear Materials for Sorting Nuclear Fuel Debris	2
Analysis of In-Vessel Actinide Transport Under Energetic CDA in an Oxide Core SFR Toward Accident Source Term Estimation	2
Some Results Concerning the Singular Solution of the Conservative Transport Equation in Spherical Geometry	2
A New Approach for NaI(Tl) Detector Efficiency Calibration Using 41Ar Radionuclide for Air Exhaust Systems	2
Bayesian Calibration and Sensitivity Analysis of Rayleigh Scattering Fiber Optic Distributed Temperature Sensing in Water Flow Loop	2
Challenges and Technology-Driven Opportunities for Safeguarding Microreactors	2
Roadmap to Right-Size Emergency Planning Zones for Microreactors	2
Thermal-Hydraulic Investigation of Steady-State Single-Phase Natural Circulation of an Integral PWR-Type SMR Test Rig (iPSTR)	2
Statistical Methods for the Study of Computer Experiment Failures: Application to a Fuel-Coolant-Interaction Simulation Code	2
Correction	2
A Benchmark for Neutron Kinetics Methods in Hexagonal Geometry	2
Hybrid Variable Selection for Estimating Nominal HEPs and PIF Multipliers for Digital Control Rooms	2
FLASSH 1.0: Thermal Scattering Law Evaluation and Cross-Section Generation for Reactor Physics Applications	2
Research on a Decision-Making Fatigue Assessment Method for Nuclear Power Plant Operators Based on Fuzzy Logic and EEG Data	2
CFD Investigations to Understand Thermal Performance of Helically Rifled Heat Transfer Enhancements in Molten Salt Applications	2
Validation of a Machine Learning–Based Nuclear Forensics Methodology for the Discrimination of a Chemically Separated Plutonium Sample from Low-Enriched Uranium	2
Development of Experimental Core Configurations to Clarify keff Variations by Nonuniform Core Configurations	2
Radiation Environment Path Planning Based on Multi-Strategy Adaptive Radiation Avoidance Ant Colony Algorithm	2
OECD/NEA TVA Watts Bar Unit 1 Benchmark: Overview of R&D and Industrial French Solutions	2
Establishment of Control Room Habitability Analysis Methodology Postulating the Event of Pressurized Tank/System of Hazardous Gas Release	2
Research on Nuclear Power Plant Operational Task Complexity Assessment Method Based on Group Decision Making and Deep Learning of EEG Signals	2
Efficient and Portable Vectorized Sweep Kernels for the Transport Equation on 3D Cartesian Grids Using the Kokkos Framework	2
Evaluation of Radiation Transport Through a Nuclear-Grade Sandwich Composite	2
Dynamic Modeling of a Fast Spectrum Molten Salt Reactor Integrated Energy System	2
Advanced Liquid-Metal-Cooled Fast Reactor Core Design Using Modern Optimization Algorithms	2
Comparative Evaluation of Spectral Methods for Robust Reactor Noise Estimation	2
Nonconforming Three-Dimensional Model for PWR Control Rod Movements Without Homogenization and Cusping Effect	2