Nuclear Science and Engineering, the research journal of the American Nuclear Society, publishes articles on research and development related to peaceful utilization of nuclear energy, radiation, and alternative energy sources.
《核科学与工程》 （英语： Nuclear Science and Engineering ）是美国核学会的研究期刊，发表与核能、辐射和替代能源的和平利用相关的研究和发展文章。
Helium Tribology of Inconel 617 at Elevated Temperatures up to 950°C: Parametric Study
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2019.1582315
High-Order Lax-Friedrichs WENO Fast Sweeping Methods for the SN Neutron Transport Equation
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2019.1582316
Numerical Simulation of Complete Pool Boiling Curves: From Nucleation to Critical Heat Flux Through Transition Boiling to Film Boiling
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2018.1504566
Benchmarks of Criticality in Solid-Moderated and Solid-Reflected Cores at Kyoto University Critical Assembly
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2018.1525978
A Note on the Nomenclature in Neutron Multiplicity Mathematics
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2018.1560758
Uncertainty Propagation in Neutron Activation Cross-Section Measurement Using Unscented Transformation Method
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2018.1538280
Review of Hybrid Methods for Deep-Penetration Neutron Transport
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2019.1586273
Gaussian Process–Based Inverse Uncertainty Quantification for TRACE Physical Model Parameters Using Steady-State PSBT Benchmark
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2018.1499279
Dynamic Mode Decomposition for Subcritical Metal Systems
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2019.1609317
A Coupled Multiscale Approach to TREAT LEU Feedback Modeling Using a Binary-Collision Monte-Carlo–Informed Heat Source
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2018.1528802
Application of Linear Combination Method to Pulsed Neutron Source Measurement at Kyoto University Critical Assembly
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2019.1624084
Constraint Annealing Method for Solution of Multiconstrained Nuclear Fuel Cycle Optimization Problems
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2018.1554173
Acceleration of the Power Method with Dynamic Mode Decomposition
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2019.1634928
Heat Loss Simulations in Rod Bundle Tests
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2018.1525189
The Asymptotic Diffusion Limit of Numerical Schemes for the SN Transport Equation
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2019.1638660
Improvement of the VVER-1200 Fuel Cycle by Introducing Thorium with Different Fissile Material in Blanket-Seed Assembly
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2018.1560757
Coupling Methods for HTR-PM Multicircuit Problem
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2018.1504545
Integral Experiments on Critical Irradiation of 237Np and 241Am Foils at Kyoto University Critical Assembly
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2019.1603014
A Multilevel in Space and Energy Solver for 3-D Multigroup Diffusion and Coarse-Mesh Finite Difference Eigenvalue Problems
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2018.1562777
An Experimental Study of Local Self-Similarity in the Mixing Transition of a Turbulent Free Jet
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2018.1507360
An Estimation of Volatile Iodine in a Pool at Low pH and High Iodide Concentrations Under Irradiation
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2019.1574118
A Diffusion Monte Carlo–Based Algorithm for Estimation of Higher Modes of a Reactor
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2019.1596721
Utilization of Regionwise Even-Parity Discontinuity Factor to Reduce Discretization Error of MOC
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2018.1516961
Large-Scale Application of the Constraint Annealing Method for Pressurized Water Reactor Core Design Optimization
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2018.1550970
Estimating Code Biases for Criticality Safety Applications with Few Relevant Benchmarks
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2019.1604048
Compression of Assembly Power Form Factors for Core Calculations
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2018.1553428
A Review of Void Drift Models in Subchannel Analysis
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2018.1525987
Coupled Neutron and Gamma Heating Calculation Based on VARIANT Transport Solutions
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2019.1621617
Validation and Verification of the Evaluated Electron Data Library in FRENSIE
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2018.1525976
Key Results from Detailed Nondestructive Examinations of 25 Pressurized Water Reactor High Burnup Spent Nuclear Fuel Rods
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2019.1573602
A New Approach to Monte Carlo in High Temperature Reactors
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2019.1576453
Development of the Assembly-Level Monte Carlo Neutron Transport Code M3C for Reactor Physics Calculations
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2019.1645502
Reactor Kinetics Using Partial Equations
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2018.1542866
Investigation of Neutron Cross Section for Iron in the ENDF Library with Pulsed Sphere Measurements
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2019.1591095
Experimental Investigation of Natural Circulation During Air-Ingress Scenario in a Very High Temperature Reactor
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2019.1595311
Scoping Studies of Dopants for Stabilization of Uranium Nitride Fuel
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2019.1614368
On CCFL at a PWR Hot-Leg Pipe Geometry and Comparison Between Results in COLLIDER 1/4th- and Kobe 1/15th-Scaled Facilities
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2018.1489627
Accelerating Monte Carlo Shielding Calculations in TRIPOLI-4 with a Deterministic Adjoint Flux
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2019.1578568
A Directional Detector Response Function for Anisotropic Detectors
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2019.1631028
Fuzzy Logics as an Integral Part of Evolutionary Algorithms
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2019.1599607
Coupling of Neutronics and Thermal-Hydraulic Codes for Simulation of the MNSR Reactor
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2019.1622927
The Roussopoulos and Schwinger Functionals for Nuclear Systems Involving Imprecisely Known Fluxes and Parameters: Distinctions and Equivalences
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2018.1564504
Approximate Methods for Inverting Generating Functions from the Pál-Bell Equations for Low Source Problems
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2018.1531620
Effects of Gamma Irradiation on the Morphological, Physical, and Thermal Properties of B4C/CF/PI/AA6061 Hybrid Composite Laminates
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2019.1654328
Assessment of nTRACER and PARCS Performance for VVER Configurations
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2020.1753418
Numerical and Experimental Study on the Air Convective Heat Transfer Characteristics in Large-Scale Rectangular Channel with Asymmetric Heating Considering the Influence of Entry Form
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2019.1591094
Tantalum, Titanium, and Zirconium Neutron Total Cross-Section Measurements from 0.4 to 25 MeV
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2019.1570750
Validation of the Interfacial Area Transport Equation Coupled with the Void Transport Equation for Prediction of Flashing Flows
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2020.1732123
Alternative Adjoint Boltzmann Transport Operators in Alternative Hilbert Spaces in Spherical Geometry: Theory and Paradigm Applications
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2019.1582934
Modeling for Late-Phase Hydrogen Generation in a Degraded Core
来源期刊：Nuclear Science and EngineeringDOI：10.1080/00295639.2018.1560855
