Nuclear Science and Engineering

Article	Citations
Data-Enabled Physics-Informed Machine Learning for Reduced-Order Modeling Digital Twin: Application to Nuclear Reactor Physics	46
Geant4 Tracks of NaI Cubic Detector Peak Efficiency, Including Coincidence Summing Correction for Rectangular Sources	17
Prediction of Neutronics Parameters Within a Two-Dimensional Reflective PWR Assembly Using Deep Learning	15
Investigation of the Influence of TeO2 on the Elastic and Radiation Shielding Capabilities of Phospho-Tellurite Glasses Doped With Sm2O3	13
A New Era of Nuclear Criticality Experiments: The First 10 Years of Planet Operations at NCERC	12
A New Era of Nuclear Criticality Experiments: The First 10 Years of Godiva IV Operations at NCERC	11
Separate-Effects Tests for Studying Temperature-Gradient-Driven Cracking in UO2 Pellets	11
Applicability of Dynamic Mode Decomposition to Estimate Fundamental Mode Component of Prompt Neutron Decay Constant from Experimental Data	10
Optimization of Beta Radioluminescent Batteries with Different Radioisotopes: A Theoretical Study	10
Reactor Physics Benchmark of the First Criticality in the Molten Salt Reactor Experiment	9
Evaluation of Yttrium Hydride (δ-YH2-x) Thermal Neutron Scattering Laws and Thermophysical Properties	8
Conceptual Design of the Transformational Challenge Reactor	8
Analysis of Population Control Techniques for Time-Dependent and Eigenvalue Monte Carlo Neutron Transport Calculations	8
Reactor Physics Considerations for Use of Yttrium Hydride Moderator	8
A New Era of Nuclear Criticality Experiments: The First 10 Years of Radiation Test Object Operations at NCERC	8
The Versatile Test Reactor Project: Mission, Requirements, and Description	8
Multiphysics Coupling Methods for Molten Salt Reactor Modeling and Simulation in VERA	7
Verification and Validation of RAPID Formulations and Algorithms Based on Dosimetry Measurements at the JSI TRIGA Mark-II Reactor	7
Development of a Sodium Fast Reactor Cartridge Loop Testing Capability for the Versatile Test Reactor	7
The ICSCREAM Methodology: Identification of Penalizing Configurations in Computer Experiments Using Screening and Metamodel—Applications in Thermal Hydraulics	7
Prediction of the Power Peaking Factor in a Boron-Free Small Modular Reactor Based on a Support Vector Regression Model and Control Rod Bank Positions	7
Optimal Batch Size Growth for Wielandt Method and Superhistory Method	7
Post-Neutron Mass Yield Distribution in the Epi-Cadmium Neutron-Induced Fission of241Am	7
Numerical Simulation on Asymmetrical Three-Dimensional Thermal and Hydraulic Characteristics of the Primary Sodium Pool Under the Pump Stuck Accident in CEFR	7
Review of the Fluid Dynamics and Heat Transport Phenomena in Packed Pebble Bed Nuclear Reactors	7

A Code-Agnostic Driver Application for Coupled Neutronics and Thermal-Hydraulic Simulations	7
MOOSE Reactor Module: An Open-Source Capability for Meshing Nuclear Reactor Geometries	6
A Robust, Relaxation-Free Multiphysics Iteration Scheme for CMFD-Accelerated Neutron Transport k-Eigenvalue Calculations—II: Numerical Results	6
TRISO SiC Failure Probability for Reactivity Initiated Accidents in High-Temperature Gas-Cooled Reactors	6
Variable Dynamic Mode Decomposition for Estimating Time Eigenvalues in Nuclear Systems	6
Post-Neutron Mass Yield Distribution in the Epi-Cadmium Neutron-Induced Fission of243Am	6
Triangular Polynomial Expansion Nodal Method for VVER Core Analysis	6
A New Era of Nuclear Criticality Experiments: The First 10 Years of Flattop Operations at NCERC	6
Generation of the Thermal Scattering Law of Uranium Dioxide with Ab Initio Lattice Dynamics to Capture Crystal Binding Effects on Neutron Interactions	6
Blind Benchmark Exercise for Spent Nuclear Fuel Decay Heat	6
A New Resonance Calculation Method Using Energy Expansion Based on a Reduced Order Model	6
Quantification of Deep Neural Network Prediction Uncertainties for VVUQ of Machine Learning Models	6
Modeling of Safety Basis Events in the VTR	6
Feasibility of Sodium-Cooled Breed-and-Burn Reactor with Rotational Fuel Shuffling	6
Uncertainty Quantification of Lead and Bismuth Sample Reactivity Worth at Kyoto University Critical Assembly	6
Transient Multilevel Scheme with One-Group CMFD Acceleration	6
A Machine Learning Method for the Forensics Attribution of Separated Plutonium	6
Post-Neutron Mass Yield Distribution in the Epi-Cadmium Neutron-Induced Fission of245Cm	6
Application of Machine Learning Algorithms to Identify Problematic Nuclear Data	6
Numerical Evaluation for Spacer Vane Effects on Flow and Heat Transfer of Water at Supercritical Pressure in Annular Channel	5
Fuel Performance Design Basis for the Versatile Test Reactor	5
Versatile Test Reactor Conceptual Core Design	5
Secondary-Source Core Reload Modeling with VERA	5
Scaling, Passive Systems, and the AP-1000	5
A New Era of Nuclear Criticality Experiments: The First 10 Years of Comet Operations at NCERC	5
A Preliminary Study on the Use of the Linear Regression Method for Multigroup Cross-Section Interpretation	5
Modeling Interface Debonding in Coated Fuel Particles with BISON	5
Probabilistic Seismic Demand Model and Seismic Fragility Analysis of NPP Equipment Subjected to High- and Low-Frequency Earthquakes	5
Neutron Balance Features in Breed-and-Burn Fast Reactors	5
OpenFOAM-Hybrid: A Morphology Adaptive Multifield Two-Fluid Model	5
Integrated Safety and Security Analysis of Nuclear Power Plants Using Dynamic Event Trees	4
Physics-Informed Neural Network Method and Application to Nuclear Reactor Calculations: A Pilot Study	4
Nuclear Reactor Power Level Model Predictive Control: A Consideration of Coolant Outlet Temperature Relaxation Tracking Method	4
Post-Neutron Mass Yield Distribution in the Epi-Cadmium Neutron-Induced Fission of229Th	4
Post-Neutron Mass Yield Distribution in the Epi-Cadmium Neutron-Induced Fission of 241 Pu	4
Real-Time Monitoring for Detection of Adversarial Subtle Process Variations	4
Strategies for Fast Fission Matrix Estimation with Fuel Temperature and Control Rod Feedback	4
Uranium Extraction from Gattar Granite Sample After Leaching Using Nitrate Solution in Presence of Peroxide	4
Introduction of the Adding and Doubling Method for Solving Bateman Equations for Nuclear Fuel Depletion	4
The Virtual Test Bed (VTB) Repository: A Library of Reference Reactor Models Using NEAMS Tools	4
Development of the Versatile Test Reactor Probabilistic Risk Assessment	4
Research on a Monte Carlo Simulation Method of Neutron Coded-Aperture Imaging	4
Multiphysics Analysis System for Heat Pipe–Cooled Micro Reactors Employing PRAGMA-OpenFOAM-ANLHTP	4
Validation and Uncertainty Quantification of Transient Reflood Models Using COBRA-TF and Machine Learning Techniques Based on the NRC/PSU RBHT Benchmark	4
Parametric Model-Order Reduction for Radiation Transport Simulations Based on an Affine Decomposition of the Operators	4
Experimental Study of Air-Steam–Mixture Condensation Underneath Containment Vessel Surface	4
Post-Neutron Mass Yield Distribution in the Epi-Cadmium Neutron-Induced Fission of237Np	4
Frequency-Dependent Discrete Implicit Monte Carlo Scheme for the Radiative Transfer Equation	4
Direct Comparison of High-Order/Low-Order Transient Methods on the 2D-LRA Benchmark Problem	4
High-Fidelity Simulation of Mixing Phenomena in Large Enclosures	4

Unstructured Mesh–Based Neutronics and Thermomechanics Coupled Steady-State Analysis on Advanced Three-Dimensional Fuel Elements with Monte Carlo Code iMC	4
Experimental and Numerical Investigation into Temperature Distribution of a Simulated PHWR Coolant Channel Under Heatup Condition	4
High-Fidelity Neutron Transport Solution of High Temperature Gas-Cooled Reactor by Three-Dimensional Linear Source Method of Characteristics	4
Study on LOFA and LOHS Accidents with Passive Safety System for Integrated Marine Reactor	4
Simulated Performance of the Micro-Pocket Fission Detector in the Advanced Test Reactor Critical Facility	4
Preliminary Analysis of Unprotected Transients in the VTR	4
Preconceptual Design of Multifunctional Gas-Cooled Cartridge Loop for the Versatile Test Reactor: Instrumentation and Measurement—Part II	4
Metallic Fuel Performance Benchmarks for Versatile Test Reactor Applications	3
An Analytic Benchmark for Neutron Boltzmann Transport with Downscattering—Part II: Flux and Eigenvalue Sensitivities to Nuclear Cross Sections and Resonance Parameters	3
Verification of Griffin-Pronghorn-Coupled Multiphysics Code System Against CNRS Molten Salt Reactor Benchmark	3
Stress Profile in Coating Layers of TRISO Fuel Particles in Contact with One Another	3
Acceleration Waves in Cylindrical Shrinking Gas Bubbles	3
Relative Speed Tabulation Method for Efficient Treatment of Resonance Scattering in GPU-Based Monte Carlo Neutron Transport Calculation	3
Benchmarking of the NCrystal SANS Plugin for Nanodiamonds	3
Development of Conceptual Lead Cartridge Design to Perform Irradiation Experiments in VTR	3
A New Calculation Strategy for Molten Salt Reactor Neutronic–Thermal-Hydraulic Analysis Implemented with APOLLO3® and TRUST/TrioCFD	3
Coupled Monte Carlo Transport and Conjugate Heat Transfer for Wire-Wrapped Bundles Within the MOOSE Framework	3
Individual Adjustment of Independent Cross-Section Set Based on Bayesian Theory	3
Investigations of Multiphysics Models on a Megawatt-Level Heat Pipe Nuclear Reactor Based on High-Fidelity Approaches	3
Extended Applications of Subgrid Representation in the 2D/1D Method	3
Silicon Solar Cells for Post-Detonation Monitoring and Gamma-Radiation Effects	3
Analyzing APR1400 System Response Under Load Follow Operation Using a Multiphysics Approach	3
Safety Analysis in VVER-1000 Due to Large-Break Loss-of-Coolant Accident and Station Blackout Transient Using RELAP5/SCDAPSIM/MOD3.5	3
FLASSH 1.0: Thermal Scattering Law Evaluation and Cross-Section Generation for Reactor Physics Applications	3
Analytical Discrete Ordinates Solution for a 1D Model of Particle Transport in Ducts that Includes Wall Migration	3
Comparisons of Supercritical Loop Flow and Heat Transfer Behavior Under Uniform and Nonuniform High-Flux Heat Inputs	3
Advances in Nuclear Data and Software Development for the HighNESS Project	3
Transport Calculation of the Multiplicity Moments for Cylinders	3
Asymptotic Expansion of the Angular Flux Applied to Discrete-Ordinates Source Iterations in Lattice Depletion Calculations	3
Digital Engineering for Integrated Modeling and Simulation for Building-Piping Systems Through Interoperability Solutions	3
The HighNESS Project at the European Spallation Source: Current Status and Future Perspectives	3
Two-Phase Turbulent Kinetic Energy Budget Computation in Co-Current Taylor Bubble Flow	3
Experimental and Computational Dose Rate Evaluation Using SN and Monte Carlo Method for a Packaged 241AmBe Neutron Source	3
A Robust, Relaxation–Free Multiphysics Iteration Scheme for CMFD–Accelerated Neutron Transport k–Eigenvalue Calculations–I: Theory	3
An Analytic Benchmark for Neutron Boltzmann Transport with Downscattering—Part I: Flux and Eigenvalue Solutions	3
A Perspective on Data-Driven Coarse Grid Modeling for System-Level Thermal Hydraulics	3
Development and Validation of Thermal-Mechanical Creep Failure Module for Reactor Pressure Vessel Lower Head	3
Post-Neutron Mass Yield Distribution in the Spontaneous Fission of252Cf	3
Frequency Transform Method for Transient Analysis of Nuclear Reactors in Monte Carlo	3
Deep Learning for Multigroup Cross-Section Representation in Two-Step Core Calculations	3
A Nonintrusive Nuclear Data Uncertainty Propagation Study for the ARC Fusion Reactor Design	3
Deceptive Infusion of Data: A Novel Data Masking Paradigm for High-Valued Systems	3
The Legendre Polynomial Axial Expansion Method	3
Investigation on the Use of the Monte Carlo Iterative k-Source Scheme for the Study of Neutron Subcritical Multiplication	3
A Novel Hybrid Deterministic and Monte Carlo Neutron Transport Formulation and Algorithm (tRAPID) for Accurate and Fast 3-D Reactor Kinetics	3
A Quasi–Monte Carlo Method With Krylov Linear Solvers for Multigroup Neutron Transport Simulations	3
Effects of Vent Size and Wind on Dispersion of Hydrogen Leaked in a Partially Open Space: Studies by Numerical Analysis	3
Gradient-Informed Design Optimization of Select Nuclear Systems	2
Sensitivity Analysis of Effectiveness of FLEX Strategies Using a CDF-Based Importance Measure Under Accident Conditions	2
Pumping Options for Versatile Test Reactor Molten Lead In-Pile Test Cartridge	2
Thermal Design and Experimental Verification of Double Helium Gap Conduction Test Facility	2
Effect of Moderation Condition on Neutron Multiplication Factor Distribution in 1/fβ Random Media	2
Nonconforming Three-Dimensional Model for PWR Control Rod Movements Without Homogenization and Cusping Effect	2
Development of Sodium Fire Analysis Code Capabilities for Versatile Test Reactor	2
A Method for Backward Failure Propagation in Conceptual System Design	2
Evaluating Quantities of Interest Other Than Nuclide Densities in the Bateman Equations	2
Application of the Gauss-Seidel Method to the Chebyshev Rational Approximation Method for Solving Nuclear Fuel Depletion Systems	2
Multidual Sensitivity Method in Ray-Tracing Transport Simulations	2
Current Status of TRIPOLI-4® Monte Carlo Radiation Transport Code on Adult and Pediatric Computational Phantoms for Radiation Dosimetry Study	2
Coupling Nuclear Predictions into Damage Simulations with SPECTRA-PKA	2
Validation of RANS-Based Turbulence Models Against High-Resolution Experiments and DNS for Buoyancy-Driven Flow with Stratified Fronts	2
Post-Neutron Mass Yield Distribution in the Thermal Neutron Induced Fission of 233U	2
Nuclear Data Uncertainty Propagation for the Molten Salt Fast Reactor Design	2
Preference-Based Multi-Robot Planning for Nuclear Power Plant Online Monitoring and Diagnostics	2
A Dynamic Risk Framework for the Physical Security of Nuclear Power Plants	2
Enhanced Cooling Characteristics of the Cylindrical Cooling Tube Using the Inserted Helical Wire Coil Based on Finite Element Analysis	2
Radiation Protection at Petawatt Laser-Driven Accelerator Facilities: The ELI Beamlines Case	2
Deterministic Transport Calculation Method for Statistical Geometry with Small Fuel Particles	2
Benchmark Experiments for Turbulent Mixing in the Scaled-Down Upper Plenum of High-Temperature Gas-Cooled Reactors Under Accident Scenario	2
Numerical Simulation of Subcooled Flow Boiling in a Vertical Annulus Channel Under Near Atmospheric Pressure Conditions	2
Radiation Dose Assessment of Tritium Released from the Thorium Molten Salt Reactor	2
Phonon Sampling Method for Inelastic Thermal Neutron Scattering Events	2
The Finite-Element with Discontiguous-Support Method	2
Supercritical Transient Analysis for Ramp Reactivity Insertion Using Multiregion Integral Kinetics Code	2
Concrete Modeling for Neutron Transport and Associated Sensitivity Studies Performed at the AMANDE-MIRCOM Facility	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
VTR Core Design Analyses Supporting Flexible Operations	2
Effects of Carbon on Void Nucleation in Self-Ion–Irradiated Pure Iron	2
The Time-Dependent Asymptotic PN Approximation for the Transport Equation	2
Linear Source Approximation in MPACT for Efficient and Robust Multiphysics Whole-Core Simulations	2

Void Reactivity in Lead and Bismuth Sample Reactivity Experiments at Kyoto University Critical Assembly	2
Proper Orthogonal Decomposition Mode Coefficient Interpolation: A Non-Intrusive Reduced-Order Model for Parametric Reactor Kinetics	2
Post-Neutron Mass Yield Distribution in the Thermal Neutron–Induced Fission of239Pu	2
Transition Core Modeling for Extended-Enrichment Accident-Tolerant Fuels in Light Water Reactors Using PARCS/Polaris	2
Benchmark Solutions for Radiative Transfer with a Moving Mesh and Exact Uncollided Source Treatments	2
A Newly Developed Suppression Pool Model Based on the ISAA Code	2
Serpent and MCNP Calculations of the Energy Deposition in the Transformational Challenge Reactor	2
Investigations of Gamma and Neutron Shielding Parameters of Ti-Nb-Fe-Cr Alloys with Varying Cr Concentrations	2
Development, Verification, and Validation of an Advanced Systems Code KP-SAM for Kairos Power Fluoride Salt–Cooled High-Temperature Reactor (KP-FHR)	2
A Critical Review of Heat Pipe Experiments in Nuclear Energy Applications	2
ROM-Based Surrogate Systems Modeling of EBR-II	2
Application of MELCOR for Simulating Molten Salt Reactor Accident Source Terms	2
A New Proof of the Asymptotic Diffusion Limit of the SN Neutron Transport Equation	2
Moment Matching: A New Optimization-Based Sampling Scheme for Uncertainty Quantification of Reactor-Physics Analysis	2
Design and Development of the 200-kW Beam Dump	2
Pressurized Water Reactor Core Power Control Using BAS-RBF-PID Approach During Transient Operation	2
Design and Control of a Fueled Molten Salt Cartridge Experiment for the Versatile Test Reactor	2
Variance Reduction and Noise Source Sampling Techniques for Monte Carlo Simulations of Neutron Noise Induced by Mechanical Vibrations	2
Multilevel-in-Space-and-Energy CMFD in VERA	2
Continuous-Energy Time-Dependent Coarse Mesh Transport (COMET) Method for Kinetics Calculations	2
A Versatile Methodology for Reactor Pressure Vessel Aging Assessments	2
A New Embedded Analysis with Pinwise Discontinuity Factors for Pin Power Reconstruction	2
Multigroup Neutron Transport Using a Collision-Based Hybrid Method	2
Design of a Fast Molten Salt Reactor for Space Nuclear Electric Propulsion	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
Simulation of the Axial-Flow Centrifugal Bubble Separator for Liquid-Fueled Molten Salt Reactors Using Eulerian Two-Fluid Model	2
Development of a 3D APOLLO3® Neutron Deterministic Calculation Scheme for the CABRI Experimental Reactor	2
Reactor Core Power Distribution Reconstruction Method by Ex-Core Detectors Based on the Correlation Effect Between Fuel Regions	2
State-of-the-Art in Evaluation Approaches for Risk Assessment of Insider Threats to Nuclear Facility Physical Protection Systems	2
Euler-Euler Model of Bubbly Flow Using Particle-Center-Averaging Method	2
Direct Numerical Simulation of High Prandtl Number Fluid Flow in the Downcomer of an Advanced Reactor	2
Transformational Challenge Reactor Safety Design and Radionuclide Retention Strategy	2
Stress Distribution and Safety Evaluation of Pipeline in Ice Plug of Nuclear Power	2
Generational Variance Reduction in Monte Carlo Criticality Simulations as a Way of Mitigating Unwanted Correlations	2
Physics-Informed Neural Network with Fourier Features for Radiation Transport in Heterogeneous Media	2
Design Optimization of the Transformational Challenge Reactor Outlet Plenum	2
Benchmarking of Stainless Steel Cube Neutron Leakage in Research Center Rez	2
Neutron Multiplicity Counting Distribution Reconstruction from Moments Using Meixner Polynomial Expansion and N-Forked Branching Approximations	2
Numerical Simulations of Passive Heat Removal from Mobile Microreactors	1
On the Assumptions Behind Statistical Sampling: A 235 U Fission Yield Uncertainty Propagation Case Study	1
Few-View CT Image Reconstruction via Least-Squares Methods: Assessment and Optimization	1
The NILO-CMFD Method for Iteratively Solving Coupled Neutron Transport–Thermal Hydraulics Problems	1
Current State of the Design Engineering of the Versatile Test Reactor Plant	1
Experimental Analysis of Fast-Transient Flow Boiling in Various Flow Conditions Using Inverse Heat Conduction Calculation Method	1
On the Numerical Method for Photofission-Based Nuclear Material Isotopic Composition Estimation in Thorium-Uranium Systems	1
Generation of Optimal Weight Values Based on the Recursive Monte Carlo Method for Use in Monte Carlo Deep Penetration Calculations	1
Design of Experiments to Support VTR Core Design	1
On the Regularity Order of the Pointwise Uncollided Angular Flux and Asymptotic Convergence of the Discrete Ordinates Approximation of the Scalar Flux	1
Modification of a Dynamic Monte Carlo Technique to Simplify and Accelerate Transient Analysis with Feedback	1
A CFD Modeling Coupled with VOF Method and Solidification Model for Molten Jet Breakup at Low Velocity	1
High-Fidelity Simulations of Shield Assembly Mixed-Convection Flows with Applications Toward Reduced-Resolution Modeling	1
An Improved Dual Asymmetric Penalized Least Squares Baseline Correction Method for High-Noise Spectral Data Analysis	1
Improved Methods for Calculating the Neutron Diffusion Coefficient of General Pebble Bed	1
Post-Neutron Fission Product Yield Distribution in the Spontaneous Fission of 244Cm	1
A Residual-Based Subgrid-Scale Method Combined with Spherical Harmonics Angular Approximation for Solving the Boltzmann Transport Equation	1
Development of Uncertainty Analysis Techniques for the Fission Matrix–Based Neutron Transport Code RAPID	1
Theoretical Derivation of a Unique Combination Number Hidden in the Higher-Order Neutron Correlation Factors Using the Pál-Bell Equation	1
Post-Neutron Mass Yield Distribution in the Thermal Neutron–Induced Fission of 235U	1
High-Order Accurate Solutions of the Point Kinetics Equations with the Spectral Deferred Correction Method	1
Preconceptual Design of Multifunctional Gas-Cooled Cartridge Loop for the Versatile Test Reactor—Part I	1
Validation and Optimization of Activity Estimates of the FiR 1 TRIGA Research Reactor Biological Shield Concrete	1
An Analysis of Transport Effects in Steady-State Simulation of the Molten Salt Reactor Experiment	1
Improvements in Computational Efficiency for Resonance Calculation Using Energy Spectrum Expansion Method	1
TRISO Burnup-Dependent Failure Analysis of a HTGR Design-Basis Accident Using BISON	1
Numerical Investigations of Molten Salt Pump Journal Bearings Under Hydrodynamic Lubrication Conditions for FHRs	1
Monte Carlo Study of an Electron-Based Neutron Source for Bragg Edge Imaging	1
Analytic Error Analysis of the Partial Derivatives Cross-Section Model—I: Derivation	1
Influence of Quantum Oscillations in the Thermal Scattering Law of Zirconium Carbide on Neutron Thermalization and Criticality	1
Physics-Informed Neural Networks for 1-D Steady-State Diffusion-Advection-Reaction Equations	1
Radiolytic Production of Fluorine Gas from MSR Relevant Fluoride Salts	1
An Asymptotic-Preserving Hybrid Angular Discretization for the Gray Radiative Transfer Equations	1
Density Wave Instability Verification of 1-D Computational Two-Fluid Model	1
Enhancing Monte Carlo Workflows for Nuclear Reactor Analysis with Metamodel-Driven Modeling	1
Development of an Activity Transport Model and In Situ Measurements on Deposited Radionuclides in the Primary Coolant Pipelines of the Chinshan Nuclear Power Plant	1
Uncertainty Quantification Approach for the Versatile Test Reactor Core Design	1
Development of NEMESI: A Multiparameter Library Generator Prototype for Industrial VVER and PWR Applications Based on APOLLO3®	1
Simulation of the Melting Behavior of the UO2-Zircaloy Fuel Cladding System by Laser Heating	1
Towards a Systematic Requirement-Based Approach to Build a Neutronics Study Platform	1
Gas-Liquid Two-Phase Flow Regime in a Horizontal Channel Under Transverse Vibration	1
Design and Thermal-Hydraulic Performance Analysis of a Low-Temperature Heat Pipe Test Facility	1
Cross Sections for Neutron Production from 6- and 10-MeV Neutrons Incident on 10B and 11B	1
A Multigroup Homogeneous Flux Reconstruction Method Based on the ANOVA-HDMR Decomposition	1
Response Matrix/Discrete Ordinates Solution of the 1D Fokker-Planck Equation	1
Beta-Ray-Bremsstrahlung Contributions to Short-Lived Delayed Photoneutron Groups in Heavy Water Reactors	1
Analytic Error Analysis of the Partial Derivatives Cross-Section Model—II: Numerical Results	1
Effectiveness of Radiation Transport Variance Reduction Methods for Wide-Area Environmental Contamination Assay Applications	1
Study of Stable Stratification in HiRJET Facility With Direct Numerical Simulation	1
Computationally Optimized Irradiation Chamber Design for Production of 135 Xe in the Washington State University TRIGA Reactor	1
Preliminary Neutronics Design and Analysis of the Fast Modular Reactor	1
A Unified Framework of Stabilized Finite Element Methods for Solving the Boltzmann Transport Equation	1
Direct Numerical Simulation of Heat Transfer in a 7-Pin Wire-Wrapped Rod Bundle	1
Estimation of Absorbed Dose due to Gas Bremsstrahlung Based on Residual Gas in Electron Storage Rings	1
Experimental Analyses of 243Am and 235U Fission Reaction Rates at Kyoto University Critical Assembly	1
Discrete-Time Bayesian Networks Applied to Flexible Coping Strategies of Nuclear Power Plant Systems	1
141Pr(α,x): New Cross-Section Data With Special Reference to 140Nd Production for Medicine	1