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 2021-05-01 to 2025-05-01.)

Article	Citations
Coupling Fixed-Source Criticality or Criticality and Shielding Modes Within TRIPOLI-4® Monte Carlo Code	67
OpenFOAM-Hybrid: A Morphology Adaptive Multifield Two-Fluid Model	17
Stability and Performance of the X-CMFD Method for Multiphysics Reactor Calculations	15
A New Era of Nuclear Criticality Experiments: The First 10 Years of Flattop Operations at NCERC	13
Uncertainty Quantification of ²³⁷ Np, ²⁴¹ Am, and ²⁴³ Am Reaction Rates in Highly Enriched Uran	12
The NILO-CMFD Method for Iteratively Solving Coupled Neutron Transport–Thermal Hydraulics Problems	11
Development of Multigroup Monte Carlo Neutron Transport Method with Regionwise Even-Parity Discontinuity Factor	11
Kinetic Theory Study of Pressure and Equation of State in a Strongly Degenerate Fermi Gas	11
High-Order Accurate Solutions of the Point Kinetics Equations with the Spectral Deferred Correction Method	10
LQG/LTR Controller Design for Power Control of Small Pressurized Water Reactors Under Four Feedback-Controlled Strategies	10
A New Calculation Method Using Pathlines for Delayed Neutron Precursors in Liquid Nuclear Fuels	10
In Situ Electronic Structure Analysis of Water-Corroded UN _x in High Vacuum	9
Advances in Nuclear Data and Software Development for the HighNESS Project	9
Analysis of Stress Corrosion Cracking Growth Rate in the Heat-Affected Zone of 316L Based on the Heterogeneity of the Mechanical Properties	9
Modeling Interface Debonding in Coated Fuel Particles with BISON	9
Decay Dose Shielding Analysis with Hybrid Unstructured Mesh/Constructive Solid Geometry Monte Carlo Calculation and ADVANTG Acceleration	9
Analysis of Major Benchmark Uncertainties for Fast Metal Assemblies in the ICSBEP Handbook	9
On the Feasibility of a RGA-Based Decoupling Control in the Reactor-Follow-Turbine Operation of a PWR	8
Estimation of Near-Field and Far-Field Post-Accident Atmospheric Dispersion for Microreactors	8
The Effects of Curved Gas-Liquid Interface on Light Reflectance Liquid Film Measurement for an Optical Waveguide Film	8
Numerical Simulations of Passive Heat Removal from Mobile Microreactors	8
Multigroup Neutron Transport Using a Collision-Based Hybrid Method	8
Proposed Enhancements to the Risk-Informed and Performance-Based Regulatory Framework for Seismic Hazard Design at NRC-Regulated Nuclear Power Plants	8
MOOSE Reactor Module: An Open-Source Capability for Meshing Nuclear Reactor Geometries	8
A Stochastic Calculus Approach to Boltzmann Transport	8

An Asymptotic-Preserving Hybrid Angular Discretization for the Gray Radiative Transfer Equations	7
Investigations of Multiphysics Models on a Megawatt-Level Heat Pipe Nuclear Reactor Based on High-Fidelity Approaches	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
Computational Fluid Dynamics Analysis of an Open-Pool Nuclear Research Reactor Core for Fluid Flow Optimization Using a Channel Box	7
Multistep Criticality Search and Power Shaping in Nuclear Microreactors with Deep Reinforcement Learning	7
Unsupervised Learning for Improved Gamma-Ray Spectrometry in Pixelated Cadmium Zinc Telluride (CZT) Detectors	7
The Effect of Branchless Collisions and Population Control on Correlations in Monte Carlo Power Iteration	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
Assessment of Modeling Decisions for Depletion Multiphysics Studies of AHTR	7
One-Dimensional Drift Flux Analysis of Bubbly Flows in Horizontal and Inclined-Upward Orientations	7
Utilizing Sensitivity and Correlation Coefficients from MCNP and Whisper to Guide Microreactor Experiment Design	6
Comparative Analysis of Standard and Advanced USL Methodologies for Nuclear Criticality Safety	6
Development of Conceptual Lead Cartridge Design to Perform Irradiation Experiments in VTR	6
Implementation and Testing of Generalized Perturbation Theory Capabilities in TRIPOLI-4®	6
Pressurized Water Reactor Core Power Control Using BAS-RBF-PID Approach During Transient Operation	6
Numerical Investigation of Process Parameter Effects on Flow Oscillations in a Natural Circulation Boiling Integral PWR-Type SMR Test Rig	6
Tool Developments in the OpenMC Code: Correlated Sampling and Transient Fission Matrix Approach Coupled to OpenFOAM	6
Variance Reduction and Noise Source Sampling Techniques for Monte Carlo Simulations of Neutron Noise Induced by Mechanical Vibrations	6
Simulation Analysis Based on Sodium-Cooled Fast Reactor Fuel Assembly Under Blockage Accident	6
Research and Application of the Rehomogenization Method for PWR Core Neutron Physics Simulation	6
A New Calculation Strategy for Molten Salt Reactor Neutronic–Thermal-Hydraulic Analysis Implemented with APOLLO3® and TRUST/TrioCFD	6
Interaction of Cesium Hydroxide with Oxide Layers Under Simulated Light Water Reactor Severe Accident	6
Probability Density Functions with Correlations of Experimental and Evaluated ²³⁵ U(n _th ,f) Fission Yields and Their Impacts on R	6
Pre-Experimental Assessment of Uranyl Nitrate Solution Irradiation in Kartini Reactor Facilities	6
Measurements of Neutron Scattering from a Copper Sample Using a Quasi-Differential Method in the Region from 2 keV to 20 MeV	5
Demonstrating a Quantitative and Systematic Approach to Reducing Excess Conservativism in Nuclear Criticality Safety Analyses	5
Alkaline Hydrolysis of Tri-iso-amyl Phosphate in n-dodecane Using Sodium Hydroxide: Part 1—Factors Affecting the Hydrolysis Process	5
The Solitary Wave in Advanced Nuclear Energy System	5
On the Accuracy of Transport Spatial Discretization Methods for Diffusive Regimes	5
Dismantling and Clearance Approach for the Swiss Light Source (SLS)	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
Lagrangian Investigation of Convective Mass Transfer of Dissolved Elements at Specimen Boundaries in a Flowing Molten Lead Loop	5
Coupling Nuclear Predictions into Damage Simulations with SPECTRA-PKA	5
Measurements of Droplet Size and Velocity Distributions During Rod Bundle Core Reflood	5
Volume Mesh–Based Monte Carlo Particle Transport with Barycentric Particle Tracking	5
Space-Dependent Calculation of the Multiplicity Moments for Shells With the Inclusion of Scattering	5
A Dynamic Risk Framework for the Physical Security of Nuclear Power Plants	5
Uncertainty Benchmarks for Time-Dependent Transport Problems	5
High-Order Finite Element Second Moment Methods for Linear Transport	4
New Measurements to Resolve Discrepancies in Evaluated Model Parameters of ¹⁸¹ Ta	4
Measurements of the Neutron Total and Capture Cross Sections and Derivation of the Resonance Parameters of ¹⁸¹ Ta	4
Axial Power Distribution Using Improved Axial Reflector Constants Calculation	4
Post-Neutron Mass Yield Distribution in the Epi-Cadmium Neutron-Induced Fission of ²⁴¹ Pu	4
Resolved Resonance Evaluation for Neutron Interactions with ¹⁰³ Rh Up to 8 keV	4
Convergence Properties of a Linear Diffusion-Acceleration Method for k-Eigenvalue Transport Problems	4
State of the Art in Cyclotrons for Radionuclide Production in Biomedicine	4
Magnetohydrodynamic Analyses of a Miniature, Dual-Stage Electromagnetic Pump for Lead and Sodium In-Pile Test Loops	4

Performance Improvement of Weight Window Method by Incorporating DXTRAN	4
Two-Step Monte Carlo Calculation Method for Sensitivity Coefficients of Reactor Period with Respect to Kinetics Parameters	4
A Parallel Coloring Newton-Krylov Method for Multiphysics Coupling System in Nuclear Reactors	4
Implementation of Resonance Upscattering Treatment in FRENDY Nuclear Data Processing System	4
Exponential Time Differencing Schemes for Fuel Depletion and Transport in Molten Salt Reactors: Theory and Implementation	4
Data-Enabled Physics-Informed Machine Learning for Reduced-Order Modeling Digital Twin: Application to Nuclear Reactor Physics	4
Some Considerations on the Equations Employed to Describe Multiplicity Moments	4
Spherical Harmonics and Discontinuous Galerkin Finite Element Methods for the Three-Dimensional Neutron Transport Equation: Application to Core and Lattice Calculation	4
Fuel Cycle Performance of the Wielenga Innovation Static Salt Reactor	4
Numerical Simulation of Turbulent Flow and Friction Characteristics Through a Loop of Narrow Rectangular Channel Under Rolling Motions	4
Effect of Internal Decay Power and Surface Cooling on Nuclear Fuel Droplet Solidification During MFCI in a SFR—A Numerical Study	4
Capability Extension of the High-Resolution Thermal-Hydraulic Code ESCOT for Hexagonal Geometry Core Multiphysics Analysis	4
Accelerator Technology for Well Logging: Advances, Challenges, and Opportunities	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
Radiation Protection at Petawatt Laser-Driven Accelerator Facilities: The ELI Beamlines Case	4
A Study of Gamma Heating, Neutron Flux, and Gamma Flux Under Several Reactor Core Conditions in the McMaster Nuclear Reactor	4
Simplified Treatment of Coating Layers in TRISO Fuel in Statistical Geometry Method in Monte Carlo Calculation	4
Reactor Physics Monitoring of a Source-Driven Subcritical System in Stationary State by Deterministic and Probabilistic Deep Neural Networks	4
Developing a Deterministic Calculation Scheme for Perturbations of In-Core Instrumentation of an MTR Core in Support of Bayesian Calibration	4
Uncertainty Analysis of the Reaction Rates in Ringhals	4
Analysis of Corner Balance Nonlinear Diffusion Acceleration and Moment-Based, Spatially Linear Transport Discretizations	4
On the Role of Axial Neutron Flux Mode Excitation in BWR Stability and Nonlinear Oscillations	4
Generalized Integral Method for Solving the Neutron Transport Equation with the Hybridized Discontinuous Galerkin Method	4
Design and Development of the 200-kW Beam Dump	4
Analysis of the Use of Different Backing Layer Materials in the Design of Alpha-Decay Sails for Interplanetary and Interstellar Travel	4
High-Order Perturbation Method for Updating Response Functions for Time-Dependent Transport Calculations	4
On the Uncertainty Analysis of the Data-Enabled Physics-Informed Neural Network for Solving Neutron Diffusion Eigenvalue Problem	4
Development and Validation of Thermal-Mechanical Creep Failure Module for Reactor Pressure Vessel Lower Head	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
Effect of Backing on Neutron Spectra for Low-Energy Quasi-Monoenergetic p + ⁷ Li Reaction	3
Investigations of Gamma and Neutron Shielding Parameters of Ti-Nb-Fe-Cr Alloys with Varying Cr Concentrations	3
First Order Response Matrix Benchmark for the 1D Transport Equation with Matrix Scaling	3
Application of MELCOR for Simulating Molten Salt Reactor Accident Source Terms	3
Study on Logging Identification of Sandstone-Type Uranium Deposits Based on Ensemble Learning in the Songliao Basin in Northeast China	3
DOE Robot Perspective: Past, Present, and Future	3
Influence of Quantum Oscillations in the Thermal Scattering Law of Zirconium Carbide on Neutron Thermalization and Criticality	3
Comparison of ²³⁸ U and ²³⁵ U Fission Chambers for Monitoring the Reactivity of the VENUS-F Accelerator-Driven Subcritical Reactor	3
Feasibility of Photonuclear Transmutation of Long-Lived Fission Products Extracted from Used Nuclear Fuel	3
A Consequence-Informed Licensing Path Selection for the Design of Physical Protection Systems at Commercial Nuclear Power Facilities	3
Ionization Efficiency Measurement and Optimization of a Thermal Ion Source for Radioisotope Electromagnetic Separation	3
Direct Numerical Simulation of High Prandtl Number Fluid Flow in the Downcomer of an Advanced Reactor	3
Design and Analyses of Miniature, Submersible Annular Linear Induction Pump for Test Loops Supporting Development of Advanced Nuclear Reactors	3
Selected papers from the 17th International Topical Meeting on Probabilistic Safety Assessment and Analysis (PSA 2021)	3
Analyzing APR1400 System Response Under Load Follow Operation Using a Multiphysics Approach	3
A Pragmatic Approach to Update Support Studies and Human Reliability Analyses for a PSA Model	3
Stress Profile in Coating Layers of TRISO Fuel Particles in Contact with One Another	3
Development of a Coupled Depletion Perturbation Theory Methodology in Continuous-Energy Monte Carlo Depletion Simulations	3
Preparation and Electrical Performance Analysis of a GaAs‐Based Tritium Battery	3
Morphological Characterization of Uranyl Fluoride Particles via Atomic Force Microscopy	3
An Iterative RSA-DEM Method for High Particle Packing Fraction Stochastic Media	3
Safety Analysis in VVER-1000 Due to Large-Break Loss-of-Coolant Accident and Station Blackout Transient Using RELAP5/SCDAPSIM/MOD3.5	3
Development, Verification, and Validation of an Advanced Systems Code KP-SAM for Kairos Power Fluoride Salt–Cooled High-Temperature Reactor (KP-FHR)	3
Void Reactivity in Lead and Bismuth Sample Reactivity Experiments at Kyoto University Critical Assembly	3
Preference-Based Multi-Robot Planning for Nuclear Power Plant Online Monitoring and Diagnostics	3
A General Formulation of the Resonance Spectrum Expansion Self-Shielding Method	3
Activation Analysis in Preparation for a Tungsten Irradiation Experiment at LANSCE	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
Radiolytic Production of Fluorine Gas from MSR Relevant Fluoride Salts	2
A Practical Comparison of Data-Driven Prognostics Methods for Energy Systems	2
Experimental Analyses of Capture Reaction Rates for Epithermal and Resonance Neutrons in Source-Driven Subcritical Cores	2
Scoping Studies for a Lead-Lithium-Cooled, Minor-Actinide-Burning, Fission-Fusion Hybrid Reactor Design	2
A Consistent Low-Order Acceleration Technique for Coarse Mesh Transport (COMET) Methods	2
Few-View CT Image Reconstruction via Least-Squares Methods: Assessment and Optimization	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 Residual-Based Subgrid-Scale Method Combined with Spherical Harmonics Angular Approximation for Solving the Boltzmann Transport Equation	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
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
MaCaw: Domain-Decomposed Monte Carlo Neutral Particle Transport on Unstructured Mesh in MOOSE	2
Physics-Informed Neural Networks for 1-D Steady-State Diffusion-Advection-Reaction Equations	2
Informing Performance Metrics of Advanced I&C Systems for Liquid Fueled Fast Molten Salt Reactors	2
Statistical Methods for the Study of Computer Experiment Failures: Application to a Fuel-Coolant-Interaction Simulation Code	2
Computationally Optimized Irradiation Chamber Design for Production of ¹³⁵ Xe in the Washington State University TRIGA Reactor	2
Using a Random Forest Model to Choose Optimized Group Structures	2
Comparing Coupled Multiphysics Simulations of Pump-Driven Transients for a Pressurized Heavy Water Reactor	2
Three-Dimensional Thermal Modeling of In Situ Heating Tests for High-Level Radioactive Nuclear Waste Repository	2
Advanced High-Temperature Sodium-Cooled Thermal Reactors Using Less Than 10% Enriched UO ₂ Fuel	2
CFD Simulation of Melt Pool Coolability in a Simulated Core Catcher Model	2
Optimization of Personnel Work Paths During Decommissioning of Nuclear Facilities	2
The Finite-Element with Discontiguous-Support Method	2

A Method to Calculate the Maturity Time for Low Neutron Source Nuclear Reactor Startup Simulations	2
On the Numerical Method for Photofission-Based Nuclear Material Isotopic Composition Estimation in Thorium-Uranium Systems	2
Experimental Estimation of the Kinetic Parameters of MINERVE Zero Power Reactor	2
The Versatile Test Reactor Project: Mission, Requirements, and Description	2
Dynamical System Scaling Application to Zircaloy Cladding Thermal Response During Reactivity-Initiated Accident Experiment	2
A Novel ERANOS Procedure for Sensitivity Analyses in Core Depletion Problems: Implementation Details and Verification	2
Core Reload Design Using Genetic Optimization for Cost Savings in a Two-Reactor Power Plant With Used Fuel Sharing	2
Neutron Noise Measurements of a Fast HEU Copper System	2
Applicability of Dynamic Mode Decomposition to Estimate Fundamental Mode Component of Prompt Neutron Decay Constant from Experimental Data	2
Improvements to the Baff-Refl Equivalence Technique Applied to Reflector Models in PWRs	2
Bayesian Estimation of Cross Section, Experimental Error, and Calculation Error: Comparison with Bias Factor Method	2
Charge Distribution Studies in the Epi-Cadmium Neutron-Induced Fission of ²⁴¹ Pu	2
Preconceptual Design of Multifunctional Gas-Cooled Cartridge Loop for the Versatile Test Reactor: Instrumentation and Measurement—Part II	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
Evaluating Quantities of Interest Other Than Nuclide Densities in the Bateman Equations	2
Numerical Investigation of Air-Steam Condensation in a Vertically Enhanced Tube with Concave and Convex Surfaces	2
Challenges and Technology-Driven Opportunities for Safeguarding Microreactors	2
Current State of the Design Engineering of the Versatile Test Reactor Plant	2
Modeling of Formation and Evolution of Cracks in Zirconium-Based Claddings of Nuclear Fuel Rods Within DIONISIO 3.0	2
Optimizations of the Accelerated Axial Polynomial Method of Characteristics of the APOLLO3® Deterministic Neutron Transport Code	2
Post-Neutron Mass Yield Distribution in the Epi-Cadmium Neutron-Induced Fission of²⁴⁵Cm	2
Welch Method and Bootstrapping Applied to Subcritical Gamma Noise	2
Impact Assessment of Radiative Heat Transport in ARC-Class Reactor FLiBe Liquid Immersion Blanket	2
CANDU Station Blackout D-PSA with RAVEN and TRACE Software	2
Thermodynamic Assessment of the NaCl-CrCl ₂ , NaCl-CrCl ₃ , and FeCl ₂ -CrCl ₂	2
Linear Source Approximation in MPACT for Efficient and Robust Multiphysics Whole-Core Simulations	2
On the Assumptions Behind Statistical Sampling: A ²³⁵ U Fission Yield Uncertainty Propagation Case Study	2
ADDENDUM: Validation of Continuous-Energy ENDF/B-VIII.0 ¹⁶O, ⁵⁶Fe, and ^63,65Cu Cross Sections for Nuclear Criticality Safety Applications	2
Technical Reviewers	2
Recent Advances in the Fenton Process for Treatment and Volume Reduction of Liquid Radioactive Waste	2
An Improved Dual Asymmetric Penalized Least Squares Baseline Correction Method for High-Noise Spectral Data Analysis	2
Numerical Investigation on the Thermal-Hydraulic Characteristics near a Corroded Lower Head of the Reactor Vessel During IVR-ERVC	2
Two-Phase Turbulent Kinetic Energy Budget Computation in Co-Current Taylor Bubble Flow	2
Flow-Induced Vibrations of Two Flexible Tubes in Cross Flow	2
An Experimental Investigation of Two-Phase Frictional Pressure Drop in Straight-Tube Steam Generator Used in SFR	2
Strategies for Fast Fission Matrix Estimation with Fuel Temperature and Control Rod Feedback	2
A Unified Framework of Stabilized Finite Element Methods for Solving the Boltzmann Transport Equation	2
Hybrid Variable Selection for Estimating Nominal HEPs and PIF Multipliers for Digital Control Rooms	2
Application of Accelerator Beam Dumps for Dark Matter Searches	2
Research on Nuclear Power Plant Operational Task Complexity Assessment Method Based on Group Decision Making and Deep Learning of EEG Signals	2
Establishment of Control Room Habitability Analysis Methodology Postulating the Event of Pressurized Tank/System of Hazardous Gas Release	2
Preliminary Neutronics Design and Analysis of the Fast Modular Reactor	2
Thermal-Hydraulic Investigation of Steady-State Single-Phase Natural Circulation of an Integral PWR-Type SMR Test Rig (iPSTR)	2
Development of Uncertainty Analysis Techniques for the Fission Matrix–Based Neutron Transport Code RAPID	2
Designing the Second Target Station with a Coupled Neutronics-Mechanical Optimization Workflow	2
Early-Stage Radiation Safety Analysis for the Spallation Neutron Source Second Target Station Bunker Operations	2
Gas-Liquid Two-Phase Flow Regime in a Horizontal Channel Under Transverse Vibration	2
Combining Similarity Measures and Left-Right Hidden Markov Models for Prognostics of Items Subjected to Perfect and Imperfect Maintenance	2
Monte Carlo Calculation Method for Reactor Period Utilizing the Differential Operator Sampling Technique	2
A Novel High-Order Surface Characteristics Scheme for the Neutron Transport Equation in 2D Unstructured Meshes	2
A Comprehensive Deep Learning–Based Approach to Field Reconstruction in Reactor Cores	1
A Nonintrusive Nuclear Data Uncertainty Propagation Study for the ARC Fusion Reactor Design	1
Special issue featuring papers from the 2022 International Conference on Physics of Reactors (PHYSOR 2022)	1
Special issue on the Nuclear Energy Advanced Modeling and Simulation Thermal Hydraulics Integrated Research Project	1
Generation IV Nuclear Reactor: Coolant Materials in the Supercritical State	1
Dependency Idioms for Quantitative Human Reliability Analysis	1
Transformational Challenge Reactor Safety Design and Radionuclide Retention Strategy	1
Validation of RANS-Based Turbulence Models Against High-Resolution Experiments and DNS for Buoyancy-Driven Flow with Stratified Fronts	1
Stochastic Optimization to Find Optimum Beginning-of-Life Core Configuration of Stable Salt Reactor with Online Refueling	1
Mitigating Spatial Error in the Iterative Quasi–Monte Carlo (iQMC) Method for Neutron Transport Simulations with Linear Discontinuous Source Tilting and Effective Scattering and Fission Rate Tallies	1
Numerical Investigations of Molten Salt Pump Journal Bearings Under Hydrodynamic Lubrication Conditions for FHRs	1
Special issue featuring papers from the SAMOSAFER Young Molten Salt Reactor Conference	1
Special issue featuring papers from the 14th International Conference on Radiation Shielding and 21st Topical Meeting of the Radiation Protection and Shielding Division (ICRS 14/RPSD 2022)	1
Kinetics Parameters Estimation for the Coupled Neutron-Photon Point Kinetics Model in Monte Carlo Eigenvalue Calculations	1
Structural, Electronic, and Mechanical Properties of α(U) and α(U-Zr) Alloy Fuels	1
Pumping Options for Versatile Test Reactor Molten Lead In-Pile Test Cartridge	1
Preliminary Analysis of Unprotected Transients in the VTR	1
The Impulse Approximation Scattering Function and Its Use in Monte Carlo Photon Transport Simulations	1
Effect of Bi ₂ O ₃ /WO ₃ on Improving the Ability of Polyepoxide-Based Composites to Attenuate	1
Convergence Study of 2D Transport Method for Multigroup k-Eigenvalue Problems with High-Order Scattering Source Using Fourier Analysis	1
Technical Reviewers	1
Goal-Oriented Mesh Adaptivity of Three-Dimensional Neutron Transport Calculation Using Weighted Difference Scheme and Dual-Weighted Residual Error Indicators	1
Multiphysics Coupling Methods for Molten Salt Reactor Modeling and Simulation in VERA	1
Digital Engineering for Integrated Modeling and Simulation for Building-Piping Systems Through Interoperability Solutions	1
Initial Verification and Validation of a New CASMO5 JENDL-5 Nuclear Data Library for Typical LWR Applications	1
Improved Collision Probability Analysis of the Double-Heterogeneity Problem Based on Matrix Chord Length Correction	1
Impact of High-Reactivity Advanced Test Reactor Experiments on Photon Heating in Nearby Experiment Locations	1
Special issue on Nuclear Physical Security Risk and Uncertainty Analysis	1
MLEM Neutron Spectra Unfolding in a Radiotherapy Bunker Using Bonner Sphere Spectrometer	1
Special issue on Advanced Reactor Thermal Hydraulics Experiments and Modeling Supporting Verification and Validation Needs	1
Parametric Model-Order Reduction for Radiation Transport Simulations Based on an Affine Decomposition of the Operators	1
Geometry Extension and Assemblywise Domain Decomposition of nTRACER for Direct Whole-Core Calculation of VVERs	1
Impact of Angular and Spatial Source Distribution Approximations on Convergence Performance of Nonlinear Acceleration Methods for MOC in Slab Geometry	1
Preliminary Design and Thermal-Hydraulic Study of a 250-kW LBE Experimental Spallation Target for CiADS	1
Mass Optimization of a Multilayered Shield for Transportable Microreactors	1
Selected papers from the 14th International Topical Meeting on Nuclear Applications of Accelerators (AccApp’21)	1
Data-Driven High-to-Low for Coarse Grid System Thermal Hydraulics	1
Development of a 3D APOLLO3® Neutron Deterministic Calculation Scheme for the CABRI Experimental Reactor	1
Variable Dynamic Mode Decomposition for Estimating Time Eigenvalues in Nuclear Systems	1
Neutron Multiplicity Counting Distribution Reconstruction from Moments Using Meixner Polynomial Expansion and N-Forked Branching Approximations	1
Validation Efforts for the Versatile Test Reactor	1
Investigation and Analysis of Beta Radioisotopes for Optimal Use in Betavoltaic Batteries	1
Design and Thermal-Hydraulic Performance Analysis of a Low-Temperature Heat Pipe Test Facility	1
The HighNESS Project at the European Spallation Source: Current Status and Future Perspectives	1
Recovering From Structural Instability in Nuclear Power Design Optimization	1