Nuclear Science and Engineering

Article	Citations
Stability and Performance of the X-CMFD Method for Multiphysics Reactor Calculations	31
High-Order Accurate Solutions of the Point Kinetics Equations with the Spectral Deferred Correction Method	24
Analysis of Major Benchmark Uncertainties for Fast Metal Assemblies in the ICSBEP Handbook	23
Advances in Nuclear Data and Software Development for the HighNESS Project	23
Uncertainty Quantification of 237 Np, 241 Am, and 243 Am Reaction Rates in Highly Enriched Uran	22
A Study of the Spatially Developing Laminar-Turbulent Transition in Rod Bundles	20
Quantifying the Effect of Material Aging on the Performance and Reliability of Passive Heat Removal Systems in Liquid Metal Fast Cooled Reactors	18
Advancing the STS Neutron Moderator Design with an Automated Optimization Workflow and Unstructured Mesh Modeling	17
Decay Dose Shielding Analysis with Hybrid Unstructured Mesh/Constructive Solid Geometry Monte Carlo Calculation and ADVANTG Acceleration	16
The NILO-CMFD Method for Iteratively Solving Coupled Neutron Transport–Thermal Hydraulics Problems	15
Analysis of Stress Corrosion Cracking Growth Rate in the Heat-Affected Zone of 316L Based on the Heterogeneity of the Mechanical Properties	14
The Effects of Curved Gas-Liquid Interface on Light Reflectance Liquid Film Measurement for an Optical Waveguide Film	14
Kinetic Theory Study of Pressure and Equation of State in a Strongly Degenerate Fermi Gas	14
Radiation-Hardened DC-DC Converter Design: Systematic Analysis of Single-Event Transient Effects and Voltage Clamping Mitigation Strategy	14
Coupling Fixed-Source Criticality or Criticality and Shielding Modes Within TRIPOLI-4® Monte Carlo Code	14
Proposed Enhancements to the Risk-Informed and Performance-Based Regulatory Framework for Seismic Hazard Design at NRC-Regulated Nuclear Power Plants	13
Predicted DBA Doses Versus Fukushima Accident Doses: A Comparative Analysis	12
On the Feasibility of a RGA-Based Decoupling Control in the Reactor-Follow-Turbine Operation of a PWR	12
A Stochastic Calculus Approach to Boltzmann Transport	12
Bubble Dynamics in a Subcooled Boiling Flow at a High Pressure	11
Nuclear Electric Propulsion for Deep-Space Missions: Technologies, Challenges, and Future Outlook	11
In Situ Electronic Structure Analysis of Water-Corroded UN x in High Vacuum	11
LQG/LTR Controller Design for Power Control of Small Pressurized Water Reactors Under Four Feedback-Controlled Strategies	11
MOOSE Reactor Module: An Open-Source Capability for Meshing Nuclear Reactor Geometries	10
Extending the Nuclide Inventory Validation Basis for High-Burnup Fuel with New Radiochemical Assay Data	10

Development of Multigroup Monte Carlo Neutron Transport Method with Regionwise Even-Parity Discontinuity Factor	10
Graph Theory and Spectral Effects in CRAM and BDF Solutions of the Nuclear Inventory Equation	10
Numerical Simulations of Passive Heat Removal from Mobile Microreactors	9
OpenFOAM-Hybrid: A Morphology Adaptive Multifield Two-Fluid Model	9
Unsupervised Learning for Improved Gamma-Ray Spectrometry in Pixelated Cadmium Zinc Telluride (CZT) Detectors	9
A New Calculation Method Using Pathlines for Delayed Neutron Precursors in Liquid Nuclear Fuels	9
MAVOR—A Tool to Create Fully Continuous, Linearized, Temperature On-the-Fly Thermal Neutron Sampling Distributions	8
Estimation of Near-Field and Far-Field Post-Accident Atmospheric Dispersion for Microreactors	8
Multigroup Neutron Transport Using a Collision-Based Hybrid Method	8
Multistep Criticality Search and Power Shaping in Nuclear Microreactors with Deep Reinforcement Learning	8
Investigations of Multiphysics Models on a Megawatt-Level Heat Pipe Nuclear Reactor Based on High-Fidelity Approaches	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
Computational Fluid Dynamics Analysis of an Open-Pool Nuclear Research Reactor Core for Fluid Flow Optimization Using a Channel Box	8
Monte Carlo and Deterministic Implementations of the Zeta-Eigenvalue Equation for Efficient Criticality Searches	8
Statistical Study of Stress and Strain in Matrix of UO 2 -Zr Plate Type Fuel	8
Probability Density Functions with Correlations of Experimental and Evaluated 235 U(n th ,f) Fission Yields and Their Impacts on R	7
Revisiting Mark’s Two-Region Problem in Spherical Geometry	7
Ants and DYN3D Solutions to the IAEA-Hex Kinetics Benchmark	7
Pre-Experimental Assessment of Uranyl Nitrate Solution Irradiation in Kartini Reactor Facilities	7
Tool Developments in the OpenMC Code: Correlated Sampling and Transient Fission Matrix Approach Coupled to OpenFOAM	7
Pressurized Water Reactor Core Power Control Using BAS-RBF-PID Approach During Transient Operation	7
Feature Selection Approaches for Gamma Spectroscopy and Weapons-Grade Plutonium Classification	7
One-Dimensional Drift Flux Analysis of Bubbly Flows in Horizontal and Inclined-Upward Orientations	7
Assessment of Modeling Decisions for Depletion Multiphysics Studies of AHTR	7
Comparative Analysis of Standard and Advanced USL Methodologies for Nuclear Criticality Safety	7
A Quasi–Monte Carlo Method With Krylov Linear Solvers for Multigroup Neutron Transport Simulations	7
The Effect of Branchless Collisions and Population Control on Correlations in Monte Carlo Power Iteration	7
Estimating the Impact of an Electromagnetic Pulse Caused by a Hypothetical Surface-Level Nuclear Explosion on Urban Critical Infrastructure	7
Development of a TRACE Critical Break LOCA Model for D-PSA Applications with RAVEN	7
Numerical Investigation of Process Parameter Effects on Flow Oscillations in a Natural Circulation Boiling Integral PWR-Type SMR Test Rig	7
Mass Yield Distributions in the 13.75-MeV Quasi-Mono-Energetic Neutron-Induced Fission of 232 Th and 238 U	7
Development of MOSCATO: A CFD-Level Electrochemistry and Corrosion Simulator for Molten Salt Systems	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
Coupling Nuclear Predictions into Damage Simulations with SPECTRA-PKA	6
Nuclear Forensics: The Ultimate Analytical Chemistry Challenge	6
Utilizing Sensitivity and Correlation Coefficients from MCNP and Whisper to Guide Microreactor Experiment Design	6
Environment Insensitive Reflector Homogenization Through a Response Matrix Equivalence Method Based on the Relaxed Flux Continuity Equation	6
Research and Application of the Rehomogenization Method for PWR Core Neutron Physics Simulation	6
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	6
On the Accuracy of Transport Spatial Discretization Methods for Diffusive Regimes	6
Uncertainty Benchmarks for Time-Dependent Transport Problems	6
Improvements in Antineutrino Spectrum by Including Fission Product Corrections and Calculation of Scatter-Based Pulse Height Distributions	6
Performance Improvement of Weight Window Method by Incorporating DXTRAN	6
Special Issue Featuring Papers from the 2024 ANS Radiation Protection and Shielding Division Topical Meeting	6
Simulation Analysis Based on Sodium-Cooled Fast Reactor Fuel Assembly Under Blockage Accident	6
A New Calculation Strategy for Molten Salt Reactor Neutronic–Thermal-Hydraulic Analysis Implemented with APOLLO3® and TRUST/TrioCFD	6
Analysis of Second Target Station Target Removal Dose Rates	6
Study on Fission Decay Width of Superheavy Nuclei 298 119 Synthesized Through the Various Fusion Reactions	6

Assessment of the Random Ray Method for Neutron Transport Problems with Strong Angular Anisotropy	6
Alkaline Hydrolysis of Tri-iso-amyl Phosphate in n-dodecane Using Sodium Hydroxide: Part 1—Factors Affecting the Hydrolysis Process	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	6
Measurements of Droplet Size and Velocity Distributions During Rod Bundle Core Reflood	6
Variance Reduction and Noise Source Sampling Techniques for Monte Carlo Simulations of Neutron Noise Induced by Mechanical Vibrations	6
Implementation and Testing of Generalized Perturbation Theory Capabilities in TRIPOLI-4®	6
Calculation of Adjoint-Weighted Kinetics Parameters in OpenMC Using the Iterated Fission Probability Method	6
Reactivity Impact of Updated 35 Cl Nuclear Data on the Molten Chloride Reactor Experiment	6
Space-Dependent Calculation of the Multiplicity Moments for Shells With the Inclusion of Scattering	5
Spatial Correlations of the Poisson Model for Radiation Transport	5
State of the Art in Cyclotrons for Radionuclide Production in Biomedicine	5
Interaction of Cesium Hydroxide with Oxide Layers Under Simulated Light Water Reactor Severe Accident	5
On the Role of Axial Neutron Flux Mode Excitation in BWR Stability and Nonlinear Oscillations	5
Capability Extension of the High-Resolution Thermal-Hydraulic Code ESCOT for Hexagonal Geometry Core Multiphysics Analysis	5
Magnetohydrodynamic Analyses of a Miniature, Dual-Stage Electromagnetic Pump for Lead and Sodium In-Pile Test Loops	5
High-Order Perturbation Method for Updating Response Functions for Time-Dependent Transport Calculations	5
An Analytic Benchmark for Neutron Boltzmann Transport with Downscattering—Part IV: PFNS and ν‾ Uncertainty Propagation	5
A 2-D Physics Study for Understanding Moderator Temperature Coefficient of Burnable Absorber–Loaded Prismatic High-Temperature Helium-Cooled Reactor	5
Two-Step Monte Carlo Calculation Method for Sensitivity Coefficients of Reactor Period with Respect to Kinetics Parameters	5
Investigations of Suction Recirculation in Primary Sodium Pump of Future Indian Fast Breeder Reactors	5
Volume Mesh–Based Monte Carlo Particle Transport with Barycentric Particle Tracking	5
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	5
Reactor Physics Monitoring of a Source-Driven Subcritical System in Stationary State by Deterministic and Probabilistic Deep Neural Networks	5
Numerical Simulation of Turbulent Flow and Friction Characteristics Through a Loop of Narrow Rectangular Channel Under Rolling Motions	5
A Dynamic Risk Framework for the Physical Security of Nuclear Power Plants	5
Design and Development of the 200-kW Beam Dump	5
Post-Neutron Mass Yield Distribution in the Epi-Cadmium Neutron-Induced Fission of 241 Pu	5
Impact of the Multigroup Velocity Approximation in the Evaluation of the Effective Neutron Lifetime	5
Effect of Internal Decay Power and Surface Cooling on Nuclear Fuel Droplet Solidification During MFCI in a SFR—A Numerical Study	5
Generalized Integral Method for Solving the Neutron Transport Equation with the Hybridized Discontinuous Galerkin Method	5
Model Predictive Control of a Small Modular Reactor with Partial Steam Diversion to Thermal Energy Storage with RELAP5-3D	5
Design and Analyses of Miniature, Submersible Annular Linear Induction Pump for Test Loops Supporting Development of Advanced Nuclear Reactors	4
Measurements of the Neutron Total and Capture Cross Sections and Derivation of the Resonance Parameters of 181 Ta	4
Interplay of Variance Reduction and Population Control in Monte Carlo Neutron Transport	4
Spherical Harmonics and Discontinuous Galerkin Finite Element Methods for the Three-Dimensional Neutron Transport Equation: Application to Core and Lattice Calculation	4
On the Uncertainty Analysis of the Data-Enabled Physics-Informed Neural Network for Solving Neutron Diffusion Eigenvalue Problem	4
High-Temperature Neutron Irradiation of Ni-Based Structural Alloys for Application in Molten Salt Nuclear Reactors	4
An S 2 Nonlinear Acceleration Scheme for Particle Transport Calculations	4
Parallel Simulated Annealing, Genetic Algorithms, and Hybrid Method Applied to the Multiobjective Optimization of the Nuclear In-Core Fuel Management	4
On MCNP Stochastic Volume Estimation Normalization	4
New Measurements to Resolve Discrepancies in Evaluated Model Parameters of 181 Ta	4
Radiation Shielding Properties of Polyethylene Reinforced with PbO and CdO: Experimental and Theoretical Study	4
Study on Logging Identification of Sandstone-Type Uranium Deposits Based on Ensemble Learning in the Songliao Basin in Northeast China	4
Void Reactivity in Lead and Bismuth Sample Reactivity Experiments at Kyoto University Critical Assembly	4
Resolved Resonance Evaluation for Neutron Interactions with 103 Rh up to 8 keV	4
Computing the Time-Averaged Nuclide Inventory Using the Chebyshev Rational Approximation Method	4
Scoping Analysis of Pebble-Bed Reactors for the Destruction of the Transuranic Inventory of LWR Spent Nuclear Fuel	4
Uncertainty Analysis of the Reaction Rates in Ringhals	4
Direct Sampling of the Egelstaff-Schofield Scattering Law and the Phonon Sampling Method for Liquids	4
Fuel Cycle Performance of the Wielenga Innovation Static Salt Reactor	4
Accelerating Long-Term Xenon Dynamics Prediction: A Reduced-Order Hybrid Recurrent Neural Network with Intrinsic Physics	4
Some Considerations on the Equations Employed to Describe Multiplicity Moments	4
Verification and Research of SGTR Accident Based on the PKL Test Facility	4
High-Order Finite Element Second Moment Methods for Linear Transport	4
Selected papers from the 17th International Topical Meeting on Probabilistic Safety Assessment and Analysis (PSA 2021)	4
Bounded Newton–Krylov Method for Chemistry-Flow–Heat Transfer Coupling Problem in High Temperature Gas-Cooled Reactors	4
Development of New GPU-Optimized Reactor Physics Monte Carlo Code GREAPMC	4
Accelerator Technology for Well Logging: Advances, Challenges, and Opportunities	4
Evaluation of PBR Spent Fuel Criticality and Dose Rate Compliance for Storage and Transportation	4
Axial Power Distribution Using Improved Axial Reflector Constants Calculation	4
A Novel Winglet-Type Arc-Vane Swirler and Its Influence on Spiral Annular Flow	4
Developing a Deterministic Calculation Scheme for Perturbations of In-Core Instrumentation of an MTR Core in Support of Bayesian Calibration	4
Characterization of a 6-kg Neptunium Metal Sphere	4
Development, Verification, and Validation of an Advanced Systems Code KP-SAM for Kairos Power Fluoride Salt–Cooled High-Temperature Reactor (KP-FHR)	4
Development of a Coupled Depletion Perturbation Theory Methodology in Continuous-Energy Monte Carlo Depletion Simulations	3
A Consequence-Informed Licensing Path Selection for the Design of Physical Protection Systems at Commercial Nuclear Power Facilities	3
Implementation of Resonance Upscattering Treatment in FRENDY Nuclear Data Processing System	3
An Iterative RSA-DEM Method for High Particle Packing Fraction Stochastic Media	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
A Parallel Coloring Newton-Krylov Method for Multiphysics Coupling System in Nuclear Reactors	3
Stability Analysis of Xenon Oscillation in PHWRs Using Modal Synthesis and Improved Quasi-Static Method: A Comparative Study	3
A General Formulation of the Resonance Spectrum Expansion Self-Shielding Method	3
Preference-Based Multi-Robot Planning for Nuclear Power Plant Online Monitoring and Diagnostics	3
Selection-Driven Evolutionary Population Control for Kinetic Monte Carlo Variance Reduction	3
Simplified Treatment of Coating Layers in TRISO Fuel in Statistical Geometry Method in Monte Carlo Calculation	3
Stress Profile in Coating Layers of TRISO Fuel Particles in Contact with One Another	3
One-Cell Inversion for Solving Higher-Order Time-Dependent Radiation Transport on GPUs	3
Multi-Objective Optimization of Uranium Target Assembly–3: A Comparison of Genetic and Traditional Methods	3
A Consistent Low-Order Acceleration Technique for Coarse Mesh Transport (COMET) Methods	3

Application of Accelerator Beam Dumps for Dark Matter Searches	3
Consistent Method for Calculating Directional Diffusion Coefficients Using Monte Carlo	3
An Experimental Investigation of Two-Phase Frictional Pressure Drop in Straight-Tube Steam Generator Used in SFR	3
Development and Validation of Thermal-Mechanical Creep Failure Module for Reactor Pressure Vessel Lower Head	3
Identification of Important Phenomena for Light Water Reactors During Heat Transport System Failure Events in Integrated Energy Systems	3
A Pragmatic Approach to Update Support Studies and Human Reliability Analyses for a PSA Model	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
Preliminary Verification of Fixed-Source Sensitivity Analysis in OpenMC	3
Investigations of Gamma and Neutron Shielding Parameters of Ti-Nb-Fe-Cr Alloys with Varying Cr Concentrations	3
Direct Numerical Simulation of High Prandtl Number Fluid Flow in the Downcomer of an Advanced Reactor	3
DOE Robot Perspective: Past, Present, and Future	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
First Order Response Matrix Benchmark for the 1D Transport Equation with Matrix Scaling	3
Radiolytic Production of Fluorine Gas from MSR Relevant Fluoride Salts	3
Optimizations of the Accelerated Axial Polynomial Method of Characteristics of the APOLLO3® Deterministic Neutron Transport Code	3
Linear Source Approximation in MPACT for Efficient and Robust Multiphysics Whole-Core Simulations	3
Computationally Optimized Irradiation Chamber Design for Production of 135 Xe in the Washington State University TRIGA Reactor	3
Bayesian Estimation of Cross Section, Experimental Error, and Calculation Error: Comparison with Bias Factor Method	3
High-Fidelity Multiphysics Modeling of the SNAP 10/A Space Reactor Using Cardinal	3
Influence of Quantum Oscillations in the Thermal Scattering Law of Zirconium Carbide on Neutron Thermalization and Criticality	3
Activation Analysis in Preparation for a Tungsten Irradiation Experiment at LANSCE	3
Optimizing Hydride Stability in U-ZrH x Nuclear Fuel: The “Goldilocks Radius”	3
Effect of Backing on Neutron Spectra for Low-Energy Quasi-Monoenergetic p +  7 Li Reaction	3
Prismatic and Pebble-Bed Micro-HTGRs in Continuous-Recycle Nuclear Fuel Cycles	3
Comparison of 238 U and 235 U Fission Chambers for Monitoring the Reactivity of the VENUS-F Accele	3
Temperature Limit of Measurement for Perovskite-Type Electrode Oxygen Sensors in Liquid LBE	3
Radiation Protection at Petawatt Laser-Driven Accelerator Facilities: The ELI Beamlines Case	3
Feasibility of Photonuclear Transmutation of Long-Lived Fission Products Extracted from Used Nuclear Fuel	3
Convergence Properties of a Linear Diffusion-Acceleration Method for k-Eigenvalue Transport Problems	3
Offline Maximizing Minimally Invasive Proper Orthogonal Decomposition for Reduced-Order Modeling of S n	3
Development of GPU-Accelerated CMFD for STREAM3D-GPU Neutron Transport Code	3
Quantification and Propagation of Uncertainties in R-Matrix Limited Resonance Parameters	3
Preparation and Electrical Performance Analysis of a GaAs‐Based Tritium Battery	3
Integrated Safety and Security Analysis of Nuclear Power Plants Using Dynamic Event Trees	3
Recent Advances in the Fenton Process for Treatment and Volume Reduction of Liquid Radioactive Waste	3
Comparing Coupled Multiphysics Simulations of Pump-Driven Transients for a Pressurized Heavy Water Reactor	3
A Method to Calculate the Maturity Time for Low Neutron Source Nuclear Reactor Startup Simulations	3
Application of MELCOR for Simulating Molten Salt Reactor Accident Source Terms	3
Importance Sampling for Monte Carlo Dynamic Event Tree Analysis of Accident Scenarios in New-Generation Nuclear Power Plants	3
Moment Asymptotics for the Neutron Transport Equation	3
An Attention-Based CNN-LSTM Model to Diagnose Break Size in Loss-of-Coolant Accidents	3
Morphological Characterization of Uranyl Fluoride Particles via Atomic Force Microscopy	3
Measurement of the Prompt Neutron Decay Constant in a Zero-Power Reactor Using a Novel 3D Detector System	2
Analysis of Sodium Spray Formation and Droplet Size Distribution Under Postulated Leak Events in SFRs for Assessment of Spray Fire Thermal Consequences	2
A Practical Comparison of Data-Driven Prognostics Methods for Energy Systems	2
Effects of Temperature and Electron Energy on the Defect Evolution Behavior of Pristine and Ion-Irradiated Yttria-Stabilized Zirconia	2
Physics-Informed Neural Networks for 1-D Steady-State Diffusion-Advection-Reaction Equations	2
On the Isotropic Approximation for Angular Flux Time Derivatives in Modeling Reactor Transients	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
Three-Dimensional Thermal Modeling of In Situ Heating Tests for High-Level Radioactive Nuclear Waste Repository	2
A Comment on a Streaming Operator that Preserves Spherical Symmetry in Cylindrical Coordinates	2
Using a Random Forest Model to Choose Optimized Group Structures	2
Thermal-Hydraulic Investigation of Steady-State Single-Phase Natural Circulation of an Integral PWR-Type SMR Test Rig (iPSTR)	2
Locational Variance in Nuclear Microreactor Performance Under Net Zero Microgrid Conditions	2
Statistical Methods for the Study of Computer Experiment Failures: Application to a Fuel-Coolant-Interaction Simulation Code	2
MaCaw: Domain-Decomposed Monte Carlo Neutral Particle Transport on Unstructured Mesh in MOOSE	2
Establishment of Control Room Habitability Analysis Methodology Postulating the Event of Pressurized Tank/System of Hazardous Gas Release	2
Accelerator-Driven Molten Salt Reactors: Studies on Neutron Efficiency and Multiplication Factor	2
Current Status of TRIPOLI-4® Monte Carlo Radiation Transport Code on Adult and Pediatric Computational Phantoms for Radiation Dosimetry Study	2
CFD Investigations to Understand Thermal Performance of Helically Rifled Heat Transfer Enhancements in Molten Salt Applications	2
Correction	2
Nondestructive Measurement Method of Nuclear Materials for Sorting Nuclear Fuel Debris	2
CANDU Station Blackout D-PSA with RAVEN and TRACE Software	2
OECD/NEA TVA Watts Bar Unit 1 Benchmark: Overview of R&D and Industrial French Solutions	2
Scoping Studies for a Lead-Lithium-Cooled, Minor-Actinide-Burning, Fission-Fusion Hybrid Reactor Design	2
Welch Method and Bootstrapping Applied to Subcritical Gamma Noise	2
Three-Dimensional Full-Core BEAVRS Using OpenMOC with Transport Equivalence	2
Continuous-Energy ENDF/B-VIII.0 Cross Section and SCALE 6.2.4 Performance for Nuclear Criticality Safety Applications: 1 H, C,	2
Multi-Physics Simulations and Sensitivity Analysis of a Main Steam Line Break Transient in a Pressurized Water Reactor	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
Analysis of In-Vessel Actinide Transport Under Energetic CDA in an Oxide Core SFR Toward Accident Source Term Estimation	2
Efficient and Portable Vectorized Sweep Kernels for the Transport Equation on 3D Cartesian Grids Using the Kokkos Framework	2
An Alternative to Probability Tables for Modeling Unresolved Resonance Behavior	2
Nonconforming Three-Dimensional Model for PWR Control Rod Movements Without Homogenization and Cusping Effect	2
DNBR Box: Enhancing the Thermal-Hydraulic Design of the Pressurized Water Reactor Protection and Surveillance Systems Using Machine Learning and Uncertainty Quantification	2
Some Results Concerning the Singular Solution of the Conservative Transport Equation in Spherical Geometry	2
Informing Performance Metrics of Advanced I&C Systems for Liquid Fueled Fast Molten Salt Reactors	2
Evaluation of Radiation Transport Through a Nuclear-Grade Sandwich Composite	2
Post-Neutron Mass Yield Distribution in the Epi-Cadmium Neutron-Induced Fission of 245 Cm	2
Monte Carlo Calculation Method for Reactor Period Utilizing the Differential Operator Sampling Technique	2
Advanced High-Temperature Sodium-Cooled Thermal Reactors Using Less Than 10% Enriched UO 2 Fuel	2
Bayesian Calibration and Sensitivity Analysis of Rayleigh Scattering Fiber Optic Distributed Temperature Sensing in Water Flow Loop	2
Hybrid Variable Selection for Estimating Nominal HEPs and PIF Multipliers for Digital Control Rooms	2
A Benchmark for Neutron Kinetics Methods in Hexagonal Geometry	2
Low-Temperature MOCVD Deposition of Vanadium Carbide on F/M Steel for Mitigating Fuel-Cladding Chemical Interaction	2
Sensitivity Analysis of an Overcooling Transient in the Generic Fluoride-Salt-Cooled High-Temperature Reactor	2
Effects of Cold Rolling–Induced Defects on Proton Irradiation Response in Nb-1Zr-0.1C Alloy	2
Study on Photon Beam Imaging Properties of CsPbBr 3 -PP Scintillator: Monte Carlo Simulation Approach	2
Challenges and Technology-Driven Opportunities for Safeguarding Microreactors	2
Development of HELIOS/BIPR/PARCS/MCNP6 Computation Route for WWER RPV Neutron Fluence Analysis and Validation Against Ex-Vessel Detector Measurement Data	2
FLASSH 1.0: Thermal Scattering Law Evaluation and Cross-Section Generation for Reactor Physics Applications	2
Research on Nuclear Power Plant Operational Task Complexity Assessment Method Based on Group Decision Making and Deep Learning of EEG Signals	2
Validation of a Machine Learning–Based Nuclear Forensics Methodology for the Discrimination of a Chemically Separated Plutonium Sample from Low-Enriched Uranium	2