Nuclear Science and Engineering
Nuclear Science and Engineering is a journal indexed in SJR in Nuclear Energy and Engineering with an H index of 68. It has an SJR impact factor of 0,657 and it has a best quartile of Q2. It is published in English. It has an SJR impact factor of 0,657.
Metrics
Scimago and CountryOfPapers database fields
SJR Impact
0,657
H-index
68
Docs (year)
273
Docs 3y
419
Total refs
7829
Cites 3y
673
Citable 3y
406
Cites/Doc 2y
1.54
Ref/Doc
28.68
Immediate OA
—
Embargoed OA
NPD
Non OA / Submission
—
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Best articles by citations
An Improved Model for Assessing the Effectiveness of Hydrogen Water Chemistry in Boiling Water Reactors
View moreWater Chemistry in the Primary Coolant Circuit of a Boiling Water Reactor during Startup Operations
View moreCoupled Fast-Thermal Power Breeder
View moreCorrosion of Materials by Liquid NaK Coolant in a Nuclear Power System
View moreConfidence Interval Procedures for Monte Carlo Transport Simulations
View moreComputation of Continuous-Energy Neutron Spectra with Discrete Ordinates Transport Theory
View moreCharacteristics, Stability, and Short-Wavelength Phenomena in Two-Phase Flow Equation Systems
View moreCharacteristics and Stability Analyses of Transient One-Dimensional Two-Phase Flow Equations and Their Finite Difference Approximations
View moreCalculation of Higher-Order Fluxes in Symmetric Cores - I: Theory
View moreB&W Spectral Shift Control Reactor Lattice Experiments: Evaluation of Core I and Core VIII
View moreApplication of the Probability Table Method to Multigroup Calculations of Neutron Transport
View moreAnalysis of KROTOS Steam Explosion Experiments Using the Improved Fuel-Coolant-Interaction Code TEXAS-VI
View moreAn Upwind Numerical Method for Two-Fluid Two-Phase Flow Models
View moreA Block Adaptive Mesh Refinement Algorithm for the Neutral Particle Transport Equation
View moreAn Assessment of Steam-Explosion-Induced Containment Failure. Part I: Probabilistic Aspects
View moreAn Assessment of Coupling Algorithms in HTR Simulator TINTE
View moreAdvanced Studies and Statistical Treatment for Sodium-Cooled Fast Reactor Pin Failures During Unprotected Transient Overpower Accident
View moreA Review of Legacy and Advanced Self-Shielding Models for Lattice Calculations
View moreA Novel, Robust Control Methodology Application to Nuclear Reactors
View moreA Model for Fission Product Release from Liquid-Metal Pools: Development and Sensitivity Investigation
View moreA Modal Expansion Equilibrium Cycle Perturbation Method for Optimizing Fast Reactors
View moreA Local Incident Flux Response Expansion Transport Method for Coupling to the Diffusion Method in Cylindrical Geometry
View moreA Hybrid Collocation-Galerkin-SnMethod for Solving the Boltzmann Transport Equation
View moreA Fluid-Bed Process for the Direct Conversion of Uranium Hexafluoride to Uranium Dioxide
View more