Nuclear Science and Engineering / Volume 197 / Number 8 / August 2023 / Pages 1545-1563
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Nuclear Science and Engineering / Volume 197 / Number 8 / August 2023 / Pages 1564-1583
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Nuclear Science and Engineering / Volume 197 / Number 8 / August 2023 / Pages 1584-1599
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Enhancing Monte Carlo Workflows for Nuclear Reactor Analysis with Metamodel-Driven Modeling
Nuclear Science and Engineering / Volume 197 / Number 8 / August 2023 / Pages 1600-1620
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Nuclear Science and Engineering / Volume 197 / Number 8 / August 2023 / Pages 1621-1633
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Nuclear Science and Engineering / Volume 197 / Number 8 / August 2023 / Pages 1634-1655
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MOOSE Reactor Module: An Open-Source Capability for Meshing Nuclear Reactor Geometries
Nuclear Science and Engineering / Volume 197 / Number 8 / August 2023 / Pages 1656-1680
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Nuclear Science and Engineering / Volume 197 / Number 8 / August 2023 / Pages 1681-1699
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An Efficient High-to-Low Iterative Method for Light Water Reactor Analysis Based on NEAMS Tools
Nuclear Science and Engineering / Volume 197 / Number 8 / August 2023 / Pages 1700-1716
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Nuclear Science and Engineering / Volume 197 / Number 8 / August 2023 / Pages 1717-1732
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Experimental Estimation of the Kinetic Parameters of MINERVE Zero Power Reactor
Nuclear Science and Engineering / Volume 197 / Number 8 / August 2023 / Pages 1733-1742
Technical papers from: PHYSOR 2022 / dx.doi.org/10.1080/00295639.2023.2174761
Multiphysics Analysis System for Heat Pipe–Cooled Micro Reactors Employing PRAGMA-OpenFOAM-ANLHTP
Nuclear Science and Engineering / Volume 197 / Number 8 / August 2023 / Pages 1743-1757
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Preliminary Neutronics Design and Analysis of the Fast Modular Reactor
Nuclear Science and Engineering / Volume 197 / Number 8 / August 2023 / Pages 1758-1768
Technical papers from: PHYSOR 2022 / dx.doi.org/10.1080/00295639.2022.2158707
Variable Dynamic Mode Decomposition for Estimating Time Eigenvalues in Nuclear Systems
Nuclear Science and Engineering / Volume 197 / Number 8 / August 2023 / Pages 1769-1778
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Nuclear Science and Engineering / Volume 197 / Number 8 / August 2023 / Pages 1779-1799
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Nuclear Science and Engineering / Volume 197 / Number 8 / August 2023 / Pages 1800-1813
Technical papers from: PHYSOR 2022 / dx.doi.org/10.1080/00295639.2022.2138063
Feynman-α Analysis Using BGO Gamma-Ray Detector in a University Training and Research Reactor
Nuclear Science and Engineering / Volume 197 / Number 8 / August 2023 / Pages 1814-1822
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High-Performance and High-Fidelity GPU-Based Monte Carlo Solutions to the BEAVRS Benchmark
Nuclear Science and Engineering / Volume 197 / Number 8 / August 2023 / Pages 1823-1844
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EBR-II MOX Fuel Characterization Enabling ARES Phase I Testing
Nuclear Science and Engineering / Volume 197 / Number 8 / August 2023 / Pages 1845-1872
Technical papers from: PHYSOR 2022 / dx.doi.org/10.1080/00295639.2022.2156240
Phonon Sampling Method for Inelastic Thermal Neutron Scattering Events
Nuclear Science and Engineering / Volume 197 / Number 8 / August 2023 / Pages 1873-1886
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Nuclear Science and Engineering / Volume 197 / Number 8 / August 2023 / Pages 1887-1901
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Nuclear Science and Engineering / Volume 197 / Number 8 / August 2023 / Pages 1902-1910
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Nuclear Science and Engineering / Volume 197 / Number 8 / August 2023 / Pages 1911-1927
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Multi-Output Gaussian Processes for Inverse Uncertainty Quantification in Neutron Noise Analysis
Nuclear Science and Engineering / Volume 197 / Number 8 / August 2023 / Pages 1928-1951
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Deep Subcriticality Determination Using the Source Jerk Integral Method in the SALMON Program
Nuclear Science and Engineering / Volume 197 / Number 8 / August 2023 / Pages 1952-1960
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Study of Reactor Core Loading Monitoring at the GUINEVERE Facility
Nuclear Science and Engineering / Volume 197 / Number 8 / August 2023 / Pages 1961-1971
Technical papers from: PHYSOR 2022 / dx.doi.org/10.1080/00295639.2022.2148813
Horizontal Split-Table Conceptual Design to Support Advanced Reactor Validation Needs
Nuclear Science and Engineering / Volume 197 / Number 8 / August 2023 / Pages 1972-1990
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State of the Art on Doppler Broadening: Modern Developments on the Fuel Temperature Coefficient
Nuclear Science and Engineering / Volume 197 / Number 8 / August 2023 / Pages 1991-2006
Technical papers from: PHYSOR 2022 / dx.doi.org/10.1080/00295639.2022.2158679
Benchmark of Neutron Thermalization in Graphite Using a Pulsed Slowing-Down-Time Experiment
Nuclear Science and Engineering / Volume 197 / Number 8 / August 2023 / Pages 2007-2016
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Nuclear Science and Engineering / Volume 197 / Number 8 / August 2023 / Pages 2017-2029
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Space-Dependent Calculation of the Multiplicity Moments for Shells With the Inclusion of Scattering
Nuclear Science and Engineering / Volume 197 / Number 8 / August 2023 / Pages 2030-2046
Technical papers from: PHYSOR 2022 / dx.doi.org/10.1080/00295639.2023.2178249
A Generalized Eigenvalue Formulation for Core-Design Applications
Nuclear Science and Engineering / Volume 197 / Number 8 / August 2023 / Pages 2047-2071
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Nuclear Science and Engineering / Volume 197 / Number 8 / August 2023 / Pages 2072-2085
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Nuclear Science and Engineering / Volume 197 / Number 8 / August 2023 / Pages 2086-2098
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Estimation of Near-Field and Far-Field Post-Accident Atmospheric Dispersion for Microreactors
Nuclear Science and Engineering / Volume 197 / Number 8 / August 2023 / Pages 2099-2116
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Using a Random Forest Model to Choose Optimized Group Structures
Nuclear Science and Engineering / Volume 197 / Number 8 / August 2023 / Pages 2117-2135
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Nuclear Science and Engineering / Volume 197 / Number 8 / August 2023 / Pages 2136-2149
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Neutronic Evaluation and Optimization of the Centrifugal Nuclear Thermal Rocket Concept
Nuclear Science and Engineering / Volume 197 / Number 8 / August 2023 / Pages 2150-2160
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Nuclear Science and Engineering / Volume 197 / Number 8 / August 2023 / Pages 2161-2175
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Design of a Fast Molten Salt Reactor for Space Nuclear Electric Propulsion
Nuclear Science and Engineering / Volume 197 / Number 8 / August 2023 / Pages 2176-2191
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A Nonintrusive Nuclear Data Uncertainty Propagation Study for the ARC Fusion Reactor Design
Nuclear Science and Engineering / Volume 197 / Number 8 / August 2023 / Pages 2192-2216
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The Virtual Test Bed (VTB) Repository: A Library of Reference Reactor Models Using NEAMS Tools
Nuclear Science and Engineering / Volume 197 / Number 8 / August 2023 / Pages 2217-2233
Technical papers from: PHYSOR 2022 / dx.doi.org/10.1080/00295639.2022.2142440
Evaluating Quantities of Interest Other Than Nuclide Densities in the Bateman Equations
Nuclear Science and Engineering / Volume 197 / Number 8 / August 2023 / Pages 2234-2250
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Nuclear Science and Engineering / Volume 197 / Number 8 / August 2023 / Pages 2251-2257
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