Nuclear Science and Engineering

Article	Citations
Deep Subcriticality Determination Using the Source Jerk Integral Method in the SALMON Program	63
Benchmark of Neutron Thermalization in Graphite Using a Pulsed Slowing-Down-Time Experiment	17
Study of Stable Stratification in HiRJET Facility With Direct Numerical Simulation	13
High-Fidelity Simulation of Mixing Phenomena in Large Enclosures	11
On the Root Structure of the Coupled Assembly Probability of Initiation Equations	11
Analyses of Critical Hydrogen Enrichment in PWR Containment Compartments	11
Feasibility of Photonuclear Transmutation of Long-Lived Fission Products Extracted from Used Nuclear Fuel	10
A Numerical Simulation of Steam Explosion in Preflooded Cavity During a Severe Accident Using the STAR-CCM+ Code	10
A Pragmatic Approach to Update Support Studies and Human Reliability Analyses for a PSA Model	9
An Iterative RSA-DEM Method for High Particle Packing Fraction Stochastic Media	9
Proposed Enhancements to the Risk-Informed and Performance-Based Regulatory Framework for Seismic Hazard Design at NRC-Regulated Nuclear Power Plants	8
The Effects of Curved Gas-Liquid Interface on Light Reflectance Liquid Film Measurement for an Optical Waveguide Film	8
Development of NEMESI: A Multiparameter Library Generator Prototype for Industrial VVER and PWR Applications Based on APOLLO3®	8
Response Matrix/Discrete Ordinates Solution of the 1D Fokker-Planck Equation	8
A Multilevel Approach for Direct Core Calculation Schemes	8
Modeling Interface Debonding in Coated Fuel Particles with BISON	8
myMUSCLE, a New Multiphysics, Multiscale Simulation Coupling Environment	7
Cross Sections for Neutron Production from 6- and 10-MeV Neutrons Incident on 10B and 11B	7
Conceptual Design of the Transformational Challenge Reactor	7
Validation of Covert Cognizance Active Defenses	7
Moment Matching: A New Optimization-Based Sampling Scheme for Uncertainty Quantification of Reactor-Physics Analysis	7
Predicting Model Biases of the APOLLO3 Neutronics Code Using Machine Learning: Toward a Multiscale and Multifidelity Approach	7
Modeling Flow Blockage Accident in Graphite-Moderated Molten Salt Reactors	7
Morphological Characterization of Uranyl Fluoride Particles via Atomic Force Microscopy	7
A Novel Core Design with Movable Moderator for a Fluoride Salt–Cooled High-Temperature Reactor	7

Feasibility of Sodium-Cooled Breed-and-Burn Reactor with Rotational Fuel Shuffling	7
Modeling and Optimization of Distillation Column for Separation of 18 O Isotope with Mathematical Model	7
Mixcoatl Software (Part 2): Verification of 1D Fluid Flow Methods Coupled to 3D FEM Thermal Diffusion Models	7
Direct Comparison of High-Order/Low-Order Transient Methods on the 2D-LRA Benchmark Problem	7
Design Optimization of the Transformational Challenge Reactor Outlet Plenum	6
Enhanced Cooling Characteristics of the Cylindrical Cooling Tube Using the Inserted Helical Wire Coil Based on Finite Element Analysis	6
Influence of Quantum Oscillations in the Thermal Scattering Law of Zirconium Carbide on Neutron Thermalization and Criticality	6
LQG/LTR Controller Design for Power Control of Small Pressurized Water Reactors Under Four Feedback-Controlled Strategies	6
Decay Dose Shielding Analysis with Hybrid Unstructured Mesh/Constructive Solid Geometry Monte Carlo Calculation and ADVANTG Acceleration	6
Analysis of Major Benchmark Uncertainties for Fast Metal Assemblies in the ICSBEP Handbook	6
Transport Corrections and Sensitivities in the Discrete-Ordinates Method	6
Stress Profile in Coating Layers of TRISO Fuel Particles in Contact with One Another	6
Modeling of Safety Basis Events in the VTR	6
Stability and Performance of the X-CMFD Method for Multiphysics Reactor Calculations	6
The Virtual Test Bed (VTB) Repository: A Library of Reference Reactor Models Using NEAMS Tools	6
Supporting Design Analysis of the VTR Using MCNP and TRACE	6
Frequency Transform Method for Transient Analysis of Nuclear Reactors in Monte Carlo	6
Monte Carlo Source Convergence Acceleration by Hybrid Multigroup and Continuous Energy Neutron Transport	6
A CFD Modeling Coupled with VOF Method and Solidification Model for Molten Jet Breakup at Low Velocity	6
High-Order Accurate Solutions of the Point Kinetics Equations with the Spectral Deferred Correction Method	6
Measurements of the 27Al(α,n) Thick Target Yield near Threshold	6
MOOSE Reactor Module: An Open-Source Capability for Meshing Nuclear Reactor Geometries	5
High-Fidelity Transient Analysis with STREAM Based on the Predictor-Corrector Quasi-Static Method	5
Advances in Nuclear Data and Software Development for the HighNESS Project	5
Numerical Evaluation of Sodium Droplet Swarm Combustion and Its Modeling Optimization	5
Development of Multiphysics Framework to Analyze Dynamic Gap Heat Transfer and Cross-Flow Effect on Partial Rod Ejection Accident	5
Simulating Fuel Assembly Bowing: A Neutron-Diffusion Method Based on Arbitrary Quadrilateral Node and Conformal Mapping Technique	5
High-Performance and High-Fidelity GPU-Based Monte Carlo Solutions to the BEAVRS Benchmark	5
A Stochastic Transport Model for the Cumulative Number of Fissions and Deposited Fission Energy	5
Photonuclear Production of 67 Cu From Gallium	5
Flux Flattening Large Heavy Water Power Reactors with Accelerator-Driven Photoneutron Source	5
Analytical Discrete Ordinates Solution for a 1D Model of Particle Transport in Ducts that Includes Wall Migration	5
Experimental Analysis of Fast-Transient Flow Boiling in Various Flow Conditions Using Inverse Heat Conduction Calculation Method	5
Generation of Optimal Weight Values Based on the Recursive Monte Carlo Method for Use in Monte Carlo Deep Penetration Calculations	5
Uncertainty Propagation of Monte Carlo Cross-Section Generation for Graphite-Moderated Pebble Bed Reactors	4
Kinetic Theory Study of Pressure and Equation of State in a Strongly Degenerate Fermi Gas	4
TRISO Burnup-Dependent Failure Analysis of a HTGR Design-Basis Accident Using BISON	4
Ionization Efficiency Measurement and Optimization of a Thermal Ion Source for Radioisotope Electromagnetic Separation	4
The NILO-CMFD Method for Iteratively Solving Coupled Neutron Transport–Thermal Hydraulics Problems	4
Activation Analysis in Preparation for a Tungsten Irradiation Experiment at LANSCE	4
Coupling Fixed-Source Criticality or Criticality and Shielding Modes Within TRIPOLI-4® Monte Carlo Code	4
Analysis of Stress Corrosion Cracking Growth Rate in the Heat-Affected Zone of 316L Based on the Heterogeneity of the Mechanical Properties	4
Study of the Accuracy of the Ronen Method at Material Interfaces	4
Nuclear Data Uncertainty Propagation for the Molten Salt Fast Reactor Design	4
Concept Descriptions for the VTR Rabbit System and Driver Fuel Test Assemblies	4
A Stochastic Calculus Approach to Boltzmann Transport	4
Evaluations of the Effect of Heterogeneity in HALEU Systems Using Modified Critical Benchmarks	4
Post-Neutron Mass Yield Distribution in the Epi-Cadmium Neutron-Induced Fission of 235 U	4
A New Era of Nuclear Criticality Experiments: The First 10 Years of Flattop Operations at NCERC	4
RGB Mapping: A Dynamic Approach for Flow Pattern Identification and Classification	4

Monte Carlo Study of an Electron-Based Neutron Source for Bragg Edge Imaging	4
T aillefer —A Tool for Sensitivity Analysis and Uncertainty Propagation Studies for Steady-State Thermal-Hydraulic Simulations of Involute Fuel Element Research Reac	4
Investigations of Gamma and Neutron Shielding Parameters of Ti-Nb-Fe-Cr Alloys with Varying Cr Concentrations	4
A Hybrid Data Assimilation and Dynamic Mode Decomposition Approach for Xenon Dynamic Prediction of Nuclear Reactor Cores	4
An Efficient High-to-Low Iterative Method for Light Water Reactor Analysis Based on NEAMS Tools	4
Code Benchmark of the HTTF Pressurized Conduction Cooldown Test Using SAM	4
Development of a Coupled Depletion Perturbation Theory Methodology in Continuous-Energy Monte Carlo Depletion Simulations	4
Uncertainty Quantification of 237 Np, 241 Am, and 243 Am Reaction Rates in Highly Enriched Uran	4
Physics-Informed Neural Network Method and Application to Nuclear Reactor Calculations: A Pilot Study	4
A Consequence-Informed Licensing Path Selection for the Design of Physical Protection Systems at Commercial Nuclear Power Facilities	4
Analysis of Postulated Accident Scenarios for the Transformational Challenge Reactor	4
Benchmark Experiments for Turbulent Mixing in the Scaled-Down Upper Plenum of High-Temperature Gas-Cooled Reactors Under Accident Scenario	4
Comparison of 238 U and 235 U Fission Chambers for Monitoring the Reactivity of the VENUS-F Accelerator-Driven Subcritical Reactor	3
Optimizing Hydride Stability in U-ZrH x Nuclear Fuel: The “Goldilocks Radius”	3
A Second Moment Method for k -Eigenvalue Acceleration with Continuous Diffusion and Discontinuous Transport Discretizations	3
Analytic Error Analysis of the Partial Derivatives Cross-Section Model—II: Numerical Results	3
An Analysis of Transport Effects in Steady-State Simulation of the Molten Salt Reactor Experiment	3
Coupled Adjoint-Based Perturbation Theory for Dynamics and Heat Transfer Multiphysics for Nuclear Transients	3
Development of Multigroup Monte Carlo Neutron Transport Method with Regionwise Even-Parity Discontinuity Factor	3
High-Resolution Modeling Without Computation Slowdown for PETALE in CROCUS	3
Experimental Investigation of the Heaving Motion Effect on Critical Heat Flux Phenomena and Wall Temperature Fluctuation Using R134a for Floating Nuclear Applications	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
In Situ Electronic Structure Analysis of Water-Corroded UN x in High Vacuum	3
Design Optimization of a Criticality Experiment for the Molten Chloride Reactor Experiment Facility	3
Numerical Simulations of Passive Heat Removal from Mobile Microreactors	3
Preparation and Electrical Performance Analysis of a GaAs‐Based Tritium Battery	3
Practical Design of a Breed-and-Burn Lead-Cooled Fast Reactor with Rotational Fuel Shuffling Strategy	3
Contribution of Lobe Power to Experiment Heating in the Advanced Test Reactor	3
Numerical Modeling and Simulation of Melting Phenomena for Freeze Valve Analysis in Molten Salt Reactors	3
Neutronic Characterization for a Pressurized Water Reactor Spent Fuel Assembly	3
The ICSCREAM Methodology: Identification of Penalizing Configurations in Computer Experiments Using Screening and Metamodel—Applications in Thermal Hydraulics	3
A New Calculation Method Using Pathlines for Delayed Neutron Precursors in Liquid Nuclear Fuels	3
Uncertainty Quantification for the Doppler Reactivity Feedback Coefficient of MYRRHA	3
On the Feasibility of a RGA-Based Decoupling Control in the Reactor-Follow-Turbine Operation of a PWR	3
Impact of Modeling Assumptions on Muon Scattering Images of Loaded Dry Storage Casks	3
Analytical Prediction of Temperature Distribution in a Deep Geological Nuclear Waste Repository	3
Neutronic and Thermodynamic System Solution of the Nuclear Power Plant	3
The LYRA-10 Experiment: Irradiation of Light Water Reactor Pressure Vessel Steels with Systematic Variations in Ni, Mn, and Si Contents to Assess Long-Term Operation–Enhanced Embrittlement	3
OpenFOAM-Hybrid: A Morphology Adaptive Multifield Two-Fluid Model	3
Simulating Properties of Canadian Research Reactor Fuels Important to Disposal	3
Development and Validation of Thermal-Mechanical Creep Failure Module for Reactor Pressure Vessel Lower Head	3
Development of the Versatile Test Reactor Probabilistic Risk Assessment	3
Effect of Backing on Neutron Spectra for Low-Energy Quasi-Monoenergetic p +  7 Li Reaction	3
Stress Distribution and Safety Evaluation of Pipeline in Ice Plug of Nuclear Power	3
From Surgical Procedures to Glovebox Processing: Enhancing Safety and Efficiency in Glovebox Operations for High-Consequence Materials	3
Verification of the Coupled Code PARCS/TWOPORFLOW with Rod Ejection Accident Calculations for Small Modular Reactors	3
Towards a Systematic Requirement-Based Approach to Build a Neutronics Study Platform	3
A New Era of Nuclear Criticality Experiments: The First 10 Years of Planet Operations at NCERC	3
Effects of Carbon on Void Nucleation in Self-Ion–Irradiated Pure Iron	2
Integrated Safety and Security Analysis of Nuclear Power Plants Using Dynamic Event Trees	2
Applicability of Dynamic Mode Decomposition to Estimate Fundamental Mode Component of Prompt Neutron Decay Constant from Experimental Data	2
A Consistent Low-Order Acceleration Technique for Coarse Mesh Transport (COMET) Methods	2
Estimation of Near-Field and Far-Field Post-Accident Atmospheric Dispersion for Microreactors	2
Improved Methods for Calculating the Neutron Diffusion Coefficient of General Pebble Bed	2
A Residual-Based Subgrid-Scale Method Combined with Spherical Harmonics Angular Approximation for Solving the Boltzmann Transport Equation	2
Structural, Electronic, and Mechanical Properties of α(U) and α(U-Zr) Alloy Fuels	2
Experimental and Computational Dose Rate Evaluation Using SN and Monte Carlo Method for a Packaged 241AmBe Neutron Source	2
Review of the Fluid Dynamics and Heat Transport Phenomena in Packed Pebble Bed Nuclear Reactors	2
Reactor Core Power Distribution Reconstruction Method by Ex-Core Detectors Based on the Correlation Effect Between Fuel Regions	2
Caustic Neutralization and Precipitation of Acidic Dissolved Simulated Stainless Steel–Clad Plutonium and Plutonium/Uranium Nuclear Fuel	2
Nuclear Data–Induced Uncertainty of Criticality in Solid-Moderated and Solid-Reflected Cores with Highly Enriched Uranium Fuel at Kyoto University Critical Assembly	2
Experimental Study of Thick Target Yield from the 13 C(α,n 0 ) 16 O Reaction	2
Optimizations of the Accelerated Axial Polynomial Method of Characteristics of the APOLLO3® Deterministic Neutron Transport Code	2
Selected papers from the 2021 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2021)	2
Density Wave Instability Verification of 1-D Computational Two-Fluid Model	2
Possible Does Not Mean Useful: The Role of Probability of Attack in Security Risk Management	2
Modification of a Dynamic Monte Carlo Technique to Simplify and Accelerate Transient Analysis with Feedback	2
Application of the Random Ray Method to Variance Reduction in Radiation Shielding Problems	2
Application of Accelerator Beam Dumps for Dark Matter Searches	2
Linear Source Approximation in MPACT for Efficient and Robust Multiphysics Whole-Core Simulations	2
Thermal Model of the AGR-5/6/7 Experiment with Offset Gas Gaps	2
Preconceptual Design of Multifunctional Gas-Cooled Cartridge Loop for the Versatile Test Reactor: Instrumentation and Measurement—Part II	2
Thermal-Mechanical Analysis of Beam Window and Beam Tube for ADS Granular Flow Target	2
EBR-II MOX Fuel Characterization Enabling ARES Phase I Testing	2
Calculation of Transient Parameters of the Integral Kinetic Model with Delayed Neutrons for Space-Dependent Kinetic Analysis of Coupled Reactors	2
Development of Sodium Fire Analysis Code Capabilities for Versatile Test Reactor	2
Dynamics of Molten Salt Reactor with Operating Heaters	2
Application of Machine Learning Algorithms to Identify Problematic Nuclear Data	2
Effect of Cladding Surface Roughness on Thermal-Hydraulic Response of Nuclear Fuel Rod of Advanced Gas-Cooled Reactor	2
Development of an Activity Transport Model and In Situ Measurements on Deposited Radionuclides in the Primary Coolant Pipelines of the Chinshan Nuclear Power Plant	2

A Modified Implicit Monte Carlo Method for Frequency-Dependent Three Temperature Radiative Transfer Equations	2
Mass Yield Distribution in the Quasi-Mono-Energetic Neutron-Induced Fission of 238 U	2
Theoretical Derivation of a Unique Combination Number Hidden in the Higher-Order Neutron Correlation Factors Using the Pál-Bell Equation	2
Application of Binary Decision Diagram Approach for Fault Tree Quantification in Seismic Probabilistic Safety Analysis of a Research Reactor	2
Selected papers from the 27th International Conference on Transport Theory (ICTT27)	2
Spatially Dependent Resonance Self-Shielding in CASMO5	2
An Experimental Investigation of Two-Phase Frictional Pressure Drop in Straight-Tube Steam Generator Used in SFR	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
An Improved Dual Asymmetric Penalized Least Squares Baseline Correction Method for High-Noise Spectral Data Analysis	2
An Analytic Benchmark for Neutron Boltzmann Transport with Downscattering—Part III: Uncertainty Propagation and Multigroup Covariance Matrices	2
A Unified Framework of Stabilized Finite Element Methods for Solving the Boltzmann Transport Equation	2
Triangular Polynomial Expansion Nodal Method for VVER Core Analysis	2
Special issue on the National Criticality Experiments Research Center	2
The Versatile Test Reactor Project: Mission, Requirements, and Description	2
Development of a Sodium Fast Reactor Cartridge Loop Testing Capability for the Versatile Test Reactor	2
Bayesian Estimation of Cross Section, Experimental Error, and Calculation Error: Comparison with Bias Factor Method	2
Multidual Sensitivity Method in Ray-Tracing Transport Simulations	2
Securing Anomaly Detection for Process-Based Time Series	2
Estimation of Absorbed Dose due to Gas Bremsstrahlung Based on Residual Gas in Electron Storage Rings	2
Corrosion of EP823 Steel Cladding Under Heavy-Liquid-Metal-Coolant Reactor Conditions: A Review	2
Technical Reviewers Nuclear Science and Engineering, 2021	2
Unsupervised Learning for Improved Gamma-Ray Spectrometry in Pixelated Cadmium Zinc Telluride (CZT) Detectors	2
Experimental Investigation of Heat Pipe Flow Dynamics and Performance	2
Asymptotic Diffusion Limits of the Multigroup Neutron Transport Equations	2
A Quasi–Monte Carlo Method With Krylov Linear Solvers for Multigroup Neutron Transport Simulations	2
Kinetics Parameters Estimation for the Coupled Neutron-Photon Point Kinetics Model in Monte Carlo Eigenvalue Calculations	2
A Versatile Methodology for Reactor Pressure Vessel Aging Assessments	2
Application of a Physics-Informed Convolutional Neural Network for Monitoring the Temperature Fields in High-Temperature Gas Reactors	2