| An Assessment of Coupling Algorithms in HTR Simulator TINTE |
13 |
| Interface Tracking Investigation of Geometric Effects on the Bubbly Flow in PWR Subchannels |
9 |
| A Linear Prolongation Approach to Stabilizing CMFD |
8 |
| The Improvement of Coupling Method in TINTE by Fully Implicit Scheme |
6 |
| Consistent pCMFD Acceleration Schemes of the Three-Dimensional Transport Code PROTEUS-MOC |
6 |
| Modeling of Resonance-Interference Effect in Depleted Fuel Compositions by Pseudo Resonant Isotopes |
5 |
| The RAPID Fission Matrix Approach to Reactor Core Criticality Calculations |
5 |
| Goal-Oriented Regional Angular Adaptive Algorithm for the S-N Equations |
5 |
| SENSMG: First-Order Sensitivities of Neutron Reaction Rates, Reaction-Rate Ratios, Leakage, k(eff) , and( )alpha Using PARTISN |
4 |
| Fission Matrix Decomposition Method for Criticality Calculations: Theory and Proof of Concept |
4 |
| Application of the Second-Order Comprehensive Adjoint Sensitivity Analysis Methodology to Compute First- and Second-Order Sensitivities of Flux Functionals in a Multiplying System with Source |
4 |
| Benchmarks of Criticality in Solid-Moderated and Solid-Reflected Cores at Kyoto University Critical Assembly |
4 |
| Review on Thermal-Hydraulic Characteristics of Nuclear Reactors Under Ocean Conditions |
4 |
| A Review of the CFD Modeling Progress Triggered by ISP-47 on Containment Thermal Hydraulics |
4 |
| Convergence Studies on Nonlinear Coarse-Mesh Finite Difference Accelerations for Neutron Transport Analysis |
4 |
| Improvements of the Embedded Self-Shielding Method with Pseudo-Resonant Isotope Model on the Multifuel Lattice System |
4 |
| Variance Estimation in Monte Carlo Eigenvalue Simulations Using Spectral Analysis Method |
4 |
| Universal Methodology for Statistical Error and Convergence of Correlated Monte Carlo Tallies |
3 |
| Investigation of (n, alpha) Reaction Cross Sections for a Number of Structural Material Isotopes |
3 |
| Calculating Time Eigenvalues of the Neutron Transport Equation with Dynamic Mode Decomposition |
3 |
| An Efficient Sweep-Based Solver for the S-N Equations on High-Order Meshes |
3 |
| Development of Generalized Perturbation Theory Algorithms for Monte Carlo Eigenvalue Calculations |
3 |
| Uncertainty Propagation in Neutron Activation Cross-Section Measurement Using Unscented Transformation Method |
3 |
| Gaussian Process-Based Inverse Uncertainty Quantification for TRACE Physical Model Parameters Using Steady-State PSBT Benchmark |
3 |
| Validation and Uncertainty Quantification for Wall Boiling Closure Relations in Multiphase-CFD Solver |
3 |
| A Note on the Nomenclature in Neutron Multiplicity Mathematics |
3 |
| High-Order Lax-Friedrichs WENO Fast Sweeping Methods for the S(N)( )Neutron Transport Equation |
3 |
| Review of Hybrid Methods for Deep-Penetration Neutron Transport |
3 |
| An Accurate Globally Conservative Subdomain Discontinuous Least-Squares Scheme for Solving Neutron Transport Problems |
3 |
| Monte Carlo Perturbation Theory Estimates of Sensitivities to System Dimensions |
3 |
| Prediction of the Prompt Neutron Multiplicity Distribution nu(A) for U-235(n, f) and Pu-239(n, f) in the Incident Energy Range of Multichance Fission |
3 |
| Helium Tribology of Inconel 617 at Elevated Temperatures up to 950 degrees C: Parametric Study |
3 |
| Uncertainty Quantification Study of CTF for the OECD/NEA LWR Uncertainty Analysis in Modeling Benchmark |
2 |
| Treatment of Double Heterogeneity in the Resonance and Thermal Energy Regions in High-Temperature Reactors |
2 |
| Multiblock Adaptive Mesh Refinement for the S-N Transport Equation Based on Lattice Boltzmann Method |
2 |
| Eigenvalue Solvers for Modeling Nuclear Reactors on Leadership Class Machines |
2 |
| A Coupled Multiscale Approach to TREAT LEU Feedback Modeling Using a Binary-Collision Monte-Carlo-Informed Heat Source |
2 |
| Modified Point-Kinetics Model for Neutron Precursors and Fission Product Behavior for Fluid-Fueled Molten Salt Reactors |
2 |
| Results of Three Neutron Diagnosed Subcritical Experiments |
2 |
| A New Collision Probability Approach for Solution of the Transport Equation in the Random Medium of High-Plutonium-Content HTR Lattice Cells |
2 |
| Calculating Alpha Eigenvalues and Eigenfunctions with a Markov Transition Rate Matrix Monte Carlo Method |
2 |
| Application of Krylov Acceleration Technique in Method of Characteristics-Based Neutron Transport Code |
2 |
| Application of Linear Combination Method to Pulsed Neutron Source Measurement at Kyoto University Critical Assembly |
2 |
| Improved Accuracy in the 2-D/1-D Method with Anisotropic Transverse Leakage and Cross-Section Homogenization |
2 |
| A Review of Molten Salt Reactor Kinetics Models |
2 |
| Acceleration and Real Variance Reduction in Continuous-Energy Monte Carlo Whole-Core Calculation via p-CMFD Feedback |
2 |
| Development, Automation, and Validation of a Numerical Methodology to Assess the TOP Onset for the RIA CABRI Experiments |
1 |
| Iteration Methods with Multigrid in Energy for Eigenvalue Neutron Diffusion Problems |
1 |
| Transient Simulations of CPR1000 Nuclear Power Plant Implementing Advanced Mechanical Shim Control System |
1 |
| Calculations and Evaluations of Neutron-Induced Reactions on Ta-180m,Ta-181 |
1 |
