OOIR: Observatory of International Research

Papers

(The median citation count of Nuclear Science and Engineering is 1. 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 2021-11-01 to 2025-11-01.)

Article	Citations
Stability and Performance of the X-CMFD Method for Multiphysics Reactor Calculations	88
High-Order Accurate Solutions of the Point Kinetics Equations with the Spectral Deferred Correction Method	22
Analysis of Major Benchmark Uncertainties for Fast Metal Assemblies in the ICSBEP Handbook	17
Advances in Nuclear Data and Software Development for the HighNESS Project	17
Uncertainty Quantification of ²³⁷ Np, ²⁴¹ Am, and ²⁴³ Am Reaction Rates in Highly Enriched Uran	15
A New Calculation Method Using Pathlines for Delayed Neutron Precursors in Liquid Nuclear Fuels	15
Numerical Simulations of Passive Heat Removal from Mobile Microreactors	14
OpenFOAM-Hybrid: A Morphology Adaptive Multifield Two-Fluid Model	14
MOOSE Reactor Module: An Open-Source Capability for Meshing Nuclear Reactor Geometries	13
A Study of the Spatially Developing Laminar-Turbulent Transition in Rod Bundles	13
The NILO-CMFD Method for Iteratively Solving Coupled Neutron Transport–Thermal Hydraulics Problems	12
Decay Dose Shielding Analysis with Hybrid Unstructured Mesh/Constructive Solid Geometry Monte Carlo Calculation and ADVANTG Acceleration	12
In Situ Electronic Structure Analysis of Water-Corroded UN _x in High Vacuum	12
Analysis of Stress Corrosion Cracking Growth Rate in the Heat-Affected Zone of 316L Based on the Heterogeneity of the Mechanical Properties	11
Kinetic Theory Study of Pressure and Equation of State in a Strongly Degenerate Fermi Gas	11
On the Feasibility of a RGA-Based Decoupling Control in the Reactor-Follow-Turbine Operation of a PWR	11
Coupling Fixed-Source Criticality or Criticality and Shielding Modes Within TRIPOLI-4® Monte Carlo Code	11
Development of Multigroup Monte Carlo Neutron Transport Method with Regionwise Even-Parity Discontinuity Factor	11
The Effects of Curved Gas-Liquid Interface on Light Reflectance Liquid Film Measurement for an Optical Waveguide Film	10
LQG/LTR Controller Design for Power Control of Small Pressurized Water Reactors Under Four Feedback-Controlled Strategies	10
Proposed Enhancements to the Risk-Informed and Performance-Based Regulatory Framework for Seismic Hazard Design at NRC-Regulated Nuclear Power Plants	10
Radiation-Hardened DC-DC Converter Design: Systematic Analysis of Single-Event Transient Effects and Voltage Clamping Mitigation Strategy	9
Quantifying the Effect of Material Aging on the Performance and Reliability of Passive Heat Removal Systems in Liquid Metal Fast Cooled Reactors	8
A Stochastic Calculus Approach to Boltzmann Transport	8
Advancing the STS Neutron Moderator Design with an Automated Optimization Workflow and Unstructured Mesh Modeling	8

Statistical Study of Stress and Strain in Matrix of UO ₂ -Zr Plate Type Fuel	8
Extending the Nuclide Inventory Validation Basis for High-Burnup Fuel with New Radiochemical Assay Data	8
Unsupervised Learning for Improved Gamma-Ray Spectrometry in Pixelated Cadmium Zinc Telluride (CZT) Detectors	8
Probability Density Functions with Correlations of Experimental and Evaluated ²³⁵ U(n _th ,f) Fission Yields and Their Impacts on R	7
Computational Fluid Dynamics Analysis of an Open-Pool Nuclear Research Reactor Core for Fluid Flow Optimization Using a Channel Box	7
Estimation of Near-Field and Far-Field Post-Accident Atmospheric Dispersion for Microreactors	7
An Asymptotic-Preserving Hybrid Angular Discretization for the Gray Radiative Transfer Equations	7
A New Calculation Strategy for Molten Salt Reactor Neutronic–Thermal-Hydraulic Analysis Implemented with APOLLO3® and TRUST/TrioCFD	7
Development of a TRACE Critical Break LOCA Model for D-PSA Applications with RAVEN	7
Estimating the Impact of an Electromagnetic Pulse Caused by a Hypothetical Surface-Level Nuclear Explosion on Urban Critical Infrastructure	7
Multigroup Neutron Transport Using a Collision-Based Hybrid Method	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
Multistep Criticality Search and Power Shaping in Nuclear Microreactors with Deep Reinforcement Learning	7
Investigations of Multiphysics Models on a Megawatt-Level Heat Pipe Nuclear Reactor Based on High-Fidelity Approaches	7
Analytic Error Analysis of the Partial Derivatives Cross-Section Model—I: Derivation	7
A Quasi–Monte Carlo Method With Krylov Linear Solvers for Multigroup Neutron Transport Simulations	7
Pressurized Water Reactor Core Power Control Using BAS-RBF-PID Approach During Transient Operation	7
One-Dimensional Drift Flux Analysis of Bubbly Flows in Horizontal and Inclined-Upward Orientations	6
Pre-Experimental Assessment of Uranyl Nitrate Solution Irradiation in Kartini Reactor Facilities	6
Mass Yield Distributions in the 13.75-MeV Quasi-Mono-Energetic Neutron-Induced Fission of ²³² Th and ²³⁸ U	6
Variance Reduction and Noise Source Sampling Techniques for Monte Carlo Simulations of Neutron Noise Induced by Mechanical Vibrations	6
Measurements of Droplet Size and Velocity Distributions During Rod Bundle Core Reflood	6
The Solitary Wave in Advanced Nuclear Energy System	6
Utilizing Sensitivity and Correlation Coefficients from MCNP and Whisper to Guide Microreactor Experiment Design	6
Analysis of Second Target Station Target Removal Dose Rates	6
Assessment of Modeling Decisions for Depletion Multiphysics Studies of AHTR	6
Research and Application of the Rehomogenization Method for PWR Core Neutron Physics Simulation	6
Comparative Analysis of Standard and Advanced USL Methodologies for Nuclear Criticality Safety	6
Performance Improvement of Weight Window Method by Incorporating DXTRAN	6
Numerical Investigation of Process Parameter Effects on Flow Oscillations in a Natural Circulation Boiling Integral PWR-Type SMR Test Rig	6
Reactivity Impact of Updated ³⁵ Cl Nuclear Data on the Molten Chloride Reactor Experiment	6
The Effect of Branchless Collisions and Population Control on Correlations in Monte Carlo Power Iteration	6
Ants and DYN3D Solutions to the IAEA-Hex Kinetics Benchmark	6
Tool Developments in the OpenMC Code: Correlated Sampling and Transient Fission Matrix Approach Coupled to OpenFOAM	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
Developing a Deterministic Calculation Scheme for Perturbations of In-Core Instrumentation of an MTR Core in Support of Bayesian Calibration	5
Volume Mesh–Based Monte Carlo Particle Transport with Barycentric Particle Tracking	5
Uncertainty Benchmarks for Time-Dependent Transport Problems	5
Computational Optimization of ^133m Xe Production via Neutron Irradiation in a TRIGA Reactor	5
Investigations of Suction Recirculation in Primary Sodium Pump of Future Indian Fast Breeder Reactors	5
Some Considerations on the Equations Employed to Describe Multiplicity Moments	5
A Dynamic Risk Framework for the Physical Security of Nuclear Power Plants	5
Spherical Harmonics and Discontinuous Galerkin Finite Element Methods for the Three-Dimensional Neutron Transport Equation: Application to Core and Lattice Calculation	5
Development of Conceptual Lead Cartridge Design to Perform Irradiation Experiments in VTR	5
Design and Development of the 200-kW Beam Dump	5
Fuel Cycle Performance of the Wielenga Innovation Static Salt Reactor	5
Impact of the Multigroup Velocity Approximation in the Evaluation of the Effective Neutron Lifetime	5
Dismantling and Clearance Approach for the Swiss Light Source (SLS)	5

Demonstrating a Quantitative and Systematic Approach to Reducing Excess Conservativism in Nuclear Criticality Safety Analyses	5
Lagrangian Investigation of Convective Mass Transfer of Dissolved Elements at Specimen Boundaries in a Flowing Molten Lead Loop	5
Space-Dependent Calculation of the Multiplicity Moments for Shells With the Inclusion of Scattering	5
Two-Step Monte Carlo Calculation Method for Sensitivity Coefficients of Reactor Period with Respect to Kinetics Parameters	5
An Analytic Benchmark for Neutron Boltzmann Transport with Downscattering—Part IV: PFNS and ν‾ Uncertainty Propagation	5
Parallel Simulated Annealing, Genetic Algorithms, and Hybrid Method Applied to the Multiobjective Optimization of the Nuclear In-Core Fuel Management	5
Numerical Simulation of Turbulent Flow and Friction Characteristics Through a Loop of Narrow Rectangular Channel Under Rolling Motions	5
Effect of Internal Decay Power and Surface Cooling on Nuclear Fuel Droplet Solidification During MFCI in a SFR—A Numerical Study	5
Improvements in Antineutrino Spectrum by Including Fission Product Corrections and Calculation of Scatter-Based Pulse Height Distributions	5
Analysis of the Use of Different Backing Layer Materials in the Design of Alpha-Decay Sails for Interplanetary and Interstellar Travel	5
Interaction of Cesium Hydroxide with Oxide Layers Under Simulated Light Water Reactor Severe Accident	5
Coupling Nuclear Predictions into Damage Simulations with SPECTRA-PKA	5
A 2-D Physics Study for Understanding Moderator Temperature Coefficient of Burnable Absorber–Loaded Prismatic High-Temperature Helium-Cooled Reactor	5
Post-Neutron Mass Yield Distribution in the Epi-Cadmium Neutron-Induced Fission of ²⁴¹ Pu	5
Alkaline Hydrolysis of Tri-iso-amyl Phosphate in n-dodecane Using Sodium Hydroxide: Part 1—Factors Affecting the Hydrolysis Process	5
Resolved Resonance Evaluation for Neutron Interactions with ¹⁰³ Rh up to 8 keV	5
Accelerator Technology for Well Logging: Advances, Challenges, and Opportunities	5
High-Order Finite Element Second Moment Methods for Linear Transport	4
DOE Robot Perspective: Past, Present, and Future	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
Void Reactivity in Lead and Bismuth Sample Reactivity Experiments at Kyoto University Critical Assembly	4
Magnetohydrodynamic Analyses of a Miniature, Dual-Stage Electromagnetic Pump for Lead and Sodium In-Pile Test Loops	4
Quantification and Propagation of Uncertainties in R-Matrix Limited Resonance Parameters	4
Computing the Time-Averaged Nuclide Inventory Using the Chebyshev Rational Approximation Method	4
On the Uncertainty Analysis of the Data-Enabled Physics-Informed Neural Network for Solving Neutron Diffusion Eigenvalue Problem	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
Scoping Analysis of Pebble-Bed Reactors for the Destruction of the Transuranic Inventory of LWR Spent Nuclear Fuel	4
Direct Numerical Simulation of High Prandtl Number Fluid Flow in the Downcomer of an Advanced Reactor	4
Simplified Treatment of Coating Layers in TRISO Fuel in Statistical Geometry Method in Monte Carlo Calculation	4
Safety Analysis in VVER-1000 Due to Large-Break Loss-of-Coolant Accident and Station Blackout Transient Using RELAP5/SCDAPSIM/MOD3.5	4
Development, Verification, and Validation of an Advanced Systems Code KP-SAM for Kairos Power Fluoride Salt–Cooled High-Temperature Reactor (KP-FHR)	4
Consistent Method for Calculating Directional Diffusion Coefficients Using Monte Carlo	4
Uncertainty Analysis of the Reaction Rates in Ringhals	4
First Order Response Matrix Benchmark for the 1D Transport Equation with Matrix Scaling	4
Capability Extension of the High-Resolution Thermal-Hydraulic Code ESCOT for Hexagonal Geometry Core Multiphysics Analysis	4
High-Order Perturbation Method for Updating Response Functions for Time-Dependent Transport Calculations	4
Reactor Physics Monitoring of a Source-Driven Subcritical System in Stationary State by Deterministic and Probabilistic Deep Neural Networks	4
Analysis of Corner Balance Nonlinear Diffusion Acceleration and Moment-Based, Spatially Linear Transport Discretizations	4
Radiation Protection at Petawatt Laser-Driven Accelerator Facilities: The ELI Beamlines Case	4
Convergence Properties of a Linear Diffusion-Acceleration Method for k-Eigenvalue Transport Problems	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
Accelerating Long-Term Xenon Dynamics Prediction: A Reduced-Order Hybrid Recurrent Neural Network with Intrinsic Physics	4
New Measurements to Resolve Discrepancies in Evaluated Model Parameters of ¹⁸¹ Ta	4
Axial Power Distribution Using Improved Axial Reflector Constants Calculation	4
Measurements of the Neutron Total and Capture Cross Sections and Derivation of the Resonance Parameters of ¹⁸¹ Ta	4
Data-Enabled Physics-Informed Machine Learning for Reduced-Order Modeling Digital Twin: Application to Nuclear Reactor Physics	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
On the Role of Axial Neutron Flux Mode Excitation in BWR Stability and Nonlinear Oscillations	4
Assessment of JEFF Nuclear Data Libraries for Reactor Physics and Spent Fuel Composition Applications	3
Comparing Coupled Multiphysics Simulations of Pump-Driven Transients for a Pressurized Heavy Water Reactor	3
Bayesian Estimation of Cross Section, Experimental Error, and Calculation Error: Comparison with Bias Factor Method	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
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
Morphological Characterization of Uranyl Fluoride Particles via Atomic Force Microscopy	3
Methodologies and Shielding Analysis for the Design of Activated Cooling Water Components in Spallation Neutron Systems	3
Interplay of Variance Reduction and Population Control in Monte Carlo Neutron Transport	3
Application of MELCOR for Simulating Molten Salt Reactor Accident Source Terms	3
On MCNP Stochastic Volume Estimation Normalization	3
Moment Asymptotics for the Neutron Transport Equation	3
Importance Sampling for Monte Carlo Dynamic Event Tree Analysis of Accident Scenarios in New-Generation Nuclear Power Plants	3
Multi-Objective Optimization of Uranium Target Assembly–3: A Comparison of Genetic and Traditional Methods	3
Experimental Analyses of Capture Reaction Rates for Epithermal and Resonance Neutrons in Source-Driven Subcritical Cores	3
A Method to Calculate the Maturity Time for Low Neutron Source Nuclear Reactor Startup Simulations	3
Optimizing Hydride Stability in U-ZrH _x Nuclear Fuel: The “Goldilocks Radius”	3
An Experimental Investigation of Two-Phase Frictional Pressure Drop in Straight-Tube Steam Generator Used in SFR	3
A Consequence-Informed Licensing Path Selection for the Design of Physical Protection Systems at Commercial Nuclear Power Facilities	3
Activation Analysis in Preparation for a Tungsten Irradiation Experiment at LANSCE	3
Identification of Important Phenomena for Light Water Reactors During Heat Transport System Failure Events in Integrated Energy Systems	3
Application of Accelerator Beam Dumps for Dark Matter Searches	3
An Iterative RSA-DEM Method for High Particle Packing Fraction Stochastic Media	3
A Parallel Coloring Newton-Krylov Method for Multiphysics Coupling System in Nuclear Reactors	3
Study on Logging Identification of Sandstone-Type Uranium Deposits Based on Ensemble Learning in the Songliao Basin in Northeast China	3
Preparation and Electrical Performance Analysis of a GaAs‐Based Tritium Battery	3

A Study on the Influence Mechanism of Cognitive Style on Situation Awareness of Nuclear Power Plant Operators	3
Physics-Informed Neural Networks for 1-D Steady-State Diffusion-Advection-Reaction Equations	3
A Consistent Low-Order Acceleration Technique for Coarse Mesh Transport (COMET) Methods	3
A Pragmatic Approach to Update Support Studies and Human Reliability Analyses for a PSA Model	3
Comparison of ²³⁸ U and ²³⁵ U Fission Chambers for Monitoring the Reactivity of the VENUS-F Accelerator-Driven Subcritical Reactor	3
Development of a Coupled Depletion Perturbation Theory Methodology in Continuous-Energy Monte Carlo Depletion Simulations	3
Stress Profile in Coating Layers of TRISO Fuel Particles in Contact with One Another	3
An Attention-Based CNN-LSTM Model to Diagnose Break Size in Loss-of-Coolant Accidents	3
Investigations of Gamma and Neutron Shielding Parameters of Ti-Nb-Fe-Cr Alloys with Varying Cr Concentrations	3
Development and Validation of Thermal-Mechanical Creep Failure Module for Reactor Pressure Vessel Lower Head	3
Influence of Quantum Oscillations in the Thermal Scattering Law of Zirconium Carbide on Neutron Thermalization and Criticality	3
Preference-Based Multi-Robot Planning for Nuclear Power Plant Online Monitoring and Diagnostics	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
Combining Similarity Measures and Left-Right Hidden Markov Models for Prognostics of Items Subjected to Perfect and Imperfect Maintenance	3
Core Reload Design Using Genetic Optimization for Cost Savings in a Two-Reactor Power Plant With Used Fuel Sharing	2
A Study of Nuclear Fuel Burnup Wave Development in a Fast Neutron Energy Spectrum Multiplying Medium: Improved Model and Consistent Parametric Approach for Evaluation	2
Post-Neutron Mass Yield Distribution in the Epi-Cadmium Neutron-Induced Fission of²⁴⁵Cm	2
Early-Stage Radiation Safety Analysis for the Spallation Neutron Source Second Target Station Bunker Operations	2
Effects of Temperature and Electron Energy on the Defect Evolution Behavior of Pristine and Ion-Irradiated Yttria-Stabilized Zirconia	2
The Versatile Test Reactor Project: Mission, Requirements, and Description	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
A Novel ERANOS Procedure for Sensitivity Analyses in Core Depletion Problems: Implementation Details and Verification	2
Analysis of Sodium Spray Formation and Droplet Size Distribution Under Postulated Leak Events in SFRs for Assessment of Spray Fire Thermal Consequences	2
Preliminary Neutronics Design and Analysis of the Fast Modular Reactor	2
Foreword	2
Current State of the Design Engineering of the Versatile Test Reactor Plant	2
Monte Carlo Calculation Method for Reactor Period Utilizing the Differential Operator Sampling Technique	2
Measurement of the Prompt Neutron Decay Constant in a Zero-Power Reactor Using a Novel 3D Detector System	2
On the Assumptions Behind Statistical Sampling: A ²³⁵ U Fission Yield Uncertainty Propagation Case Study	2
Blind Benchmark Exercise for Spent Nuclear Fuel Decay Heat	2
Thermodynamic Assessment of the NaCl-CrCl ₂ , NaCl-CrCl ₃ , and FeCl ₂ -CrCl ₂	2
Sensitivity Analysis of an Overcooling Transient in the Generic Fluoride-Salt-Cooled High-Temperature Reactor	2
Preconceptual Design of Multifunctional Gas-Cooled Cartridge Loop for the Versatile Test Reactor: Instrumentation and Measurement—Part II	2
Study on Photon Beam Imaging Properties of CsPbBr ₃ -PP Scintillator: Monte Carlo Simulation Approach	2
A Residual-Based Subgrid-Scale Method Combined with Spherical Harmonics Angular Approximation for Solving the Boltzmann Transport Equation	2
Nonconforming Three-Dimensional Model for PWR Control Rod Movements Without Homogenization and Cusping Effect	2
One-Cell Inversion for Solving Higher-Order Time-Dependent Radiation Transport on GPUs	2
Informing Performance Metrics of Advanced I&C Systems for Liquid Fueled Fast Molten Salt Reactors	2
Hybrid Variable Selection for Estimating Nominal HEPs and PIF Multipliers for Digital Control Rooms	2
Demonstration of TOFFEE: A Response Uncertainty Quantification Tool	2
Welch Method and Bootstrapping Applied to Subcritical Gamma Noise	2
Advanced High-Temperature Sodium-Cooled Thermal Reactors Using Less Than 10% Enriched UO ₂ Fuel	2
Designing the Second Target Station with a Coupled Neutronics-Mechanical Optimization Workflow	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
Two-Phase Turbulent Kinetic Energy Budget Computation in Co-Current Taylor Bubble Flow	2
Nondestructive Measurement Method of Nuclear Materials for Sorting Nuclear Fuel Debris	2
Computationally Optimized Irradiation Chamber Design for Production of ¹³⁵ Xe in the Washington State University TRIGA Reactor	2
Few-View CT Image Reconstruction via Least-Squares Methods: Assessment and Optimization	2
MaCaw: Domain-Decomposed Monte Carlo Neutral Particle Transport on Unstructured Mesh in MOOSE	2
CFD Simulation of Melt Pool Coolability in a Simulated Core Catcher Model	2
CANDU Station Blackout D-PSA with RAVEN and TRACE Software	2
Establishment of Control Room Habitability Analysis Methodology Postulating the Event of Pressurized Tank/System of Hazardous Gas Release	2
On the Numerical Method for Photofission-Based Nuclear Material Isotopic Composition Estimation in Thorium-Uranium Systems	2
Low-Temperature MOCVD Deposition of Vanadium Carbide on F/M Steel for Mitigating Fuel-Cladding Chemical Interaction	2
Development of Uncertainty Analysis Techniques for the Fission Matrix–Based Neutron Transport Code RAPID	2
Effects of Cold Rolling–Induced Defects on Proton Irradiation Response in Nb-1Zr-0.1C Alloy	2
Gas-Liquid Two-Phase Flow Regime in a Horizontal Channel Under Transverse Vibration	2
Advanced Liquid-Metal-Cooled Fast Reactor Core Design Using Modern Optimization Algorithms	2
Experimental Estimation of the Kinetic Parameters of MINERVE Zero Power Reactor	2
Efficient and Portable Vectorized Sweep Kernels for the Transport Equation on 3D Cartesian Grids Using the Kokkos Framework	2
Evaluating Quantities of Interest Other Than Nuclide Densities in the Bateman Equations	2
Thermal-Hydraulic Investigation of Steady-State Single-Phase Natural Circulation of an Integral PWR-Type SMR Test Rig (iPSTR)	2
FLASSH 1.0: Thermal Scattering Law Evaluation and Cross-Section Generation for Reactor Physics Applications	2
Neutron Noise Measurements of a Fast HEU Copper System	2
Technical Reviewers	2
Recent Advances in the Fenton Process for Treatment and Volume Reduction of Liquid Radioactive Waste	2
Numerical Investigation on the Thermal-Hydraulic Characteristics near a Corroded Lower Head of the Reactor Vessel During IVR-ERVC	2
Flow-Induced Vibrations of Two Flexible Tubes in Cross Flow	2
Charge Distribution Studies in the Epi-Cadmium Neutron-Induced Fission of ²⁴¹ Pu	2
Linear Source Approximation in MPACT for Efficient and Robust Multiphysics Whole-Core Simulations	2
Numerical Investigation of Air-Steam Condensation in a Vertically Enhanced Tube with Concave and Convex Surfaces	2
Optimization of Personnel Work Paths During Decommissioning of Nuclear Facilities	2
Scoping Studies for a Lead-Lithium-Cooled, Minor-Actinide-Burning, Fission-Fusion Hybrid Reactor Design	2
Radiolytic Production of Fluorine Gas from MSR Relevant Fluoride Salts	2
A Path Planning Algorithm Considering the Feasibility Region of Nuclear Decommissioning Robots	2
Statistical Methods for the Study of Computer Experiment Failures: Application to a Fuel-Coolant-Interaction Simulation Code	2
A Practical Comparison of Data-Driven Prognostics Methods for Energy Systems	2
CFD Investigations to Understand Thermal Performance of Helically Rifled Heat Transfer Enhancements in Molten Salt Applications	2
Impact Assessment of Radiative Heat Transport in ARC-Class Reactor FLiBe Liquid Immersion Blanket	2
Using a Random Forest Model to Choose Optimized Group Structures	2
A Novel High-Order Surface Characteristics Scheme for the Neutron Transport Equation in 2D Unstructured Meshes	2
Three-Dimensional Thermal Modeling of In Situ Heating Tests for High-Level Radioactive Nuclear Waste Repository	2
A Unified Framework of Stabilized Finite Element Methods for Solving the Boltzmann Transport Equation	2
Locational Variance in Nuclear Microreactor Performance Under Net Zero Microgrid Conditions	2
Integrated Safety and Security Analysis of Nuclear Power Plants Using Dynamic Event Trees	2
Development of HELIOS/BIPR/PARCS/MCNP6 Computation Route for WWER RPV Neutron Fluence Analysis and Validation Against Ex-Vessel Detector Measurement Data	2
Optimizations of the Accelerated Axial Polynomial Method of Characteristics of the APOLLO3® Deterministic Neutron Transport Code	2
Improvements to the Baff-Refl Equivalence Technique Applied to Reflector Models in PWRs	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
Real-Time State Estimation of Neutron Flux in Molten Salt Fast Reactors from Out-Core Sparse Measurements	2
A High-Throughput Hot Surface Ion Source for Electromagnetic Radioisotope Separation	1
Transformational Challenge Reactor Safety Design and Radionuclide Retention Strategy	1
Stochastic Optimization to Find Optimum Beginning-of-Life Core Configuration of Stable Salt Reactor with Online Refueling	1
Dependency Idioms for Quantitative Human Reliability Analysis	1
Uncertainty Quantification Framework for High-Temperature Gas-Cooled Reactors Using VSOP and DAKOTA	1