Annals of Nuclear Energy

Papers
(The H4-Index of Annals of Nuclear Energy is 33. The table below lists those papers that are above that threshold based on CrossRef citation counts [max. 250 papers]. The publications cover those that have been published in the past four years, i.e., from 2022-06-01 to 2026-06-01.)
ArticleCitations
Editorial Board83
Monte Carlo transport correction for graphite-moderated nuclear reactors using the Cumulative Migration Method77
Radiation survey for Taiwan research reactor vessel69
Impact of experimental effects on a resolved resonance evaluation for practical applications65
Development of lumped-parameter models for debris bed remelting analysis64
Thermionic conversion performance analysis of the single-cell thermionic fuel element based on FROBA-THERMION code64
Numerical study on heat transfer and flow oscillations of supercritical-pressure water in helical tubes58
Numerical analysis on steam–air condensation at low wall sub-cooling under natural convection47
Neutron transmission measurements for silica glass at the KURNS-LINAC46
Influence of PCHE size and types on thermodynamic and economic performance of supercritical carbon dioxide Brayton cycle for small modular reactors and its optimization45
A molten salt test loop for component and instrumentation testing44
Experimental analysis of boron dilution transient flow mixing characteristics based on planar laser induced fluorescence measurement44
Online inventory modeling of a CANDU-6 reactor for nuclear forensic applications44
Barium-calcium-lead-borate glasses: A new extent optimization of gamma-ray shielding43
An investigation of structural strength of PWR fuel assembly spacer grid with fuel rod clad43
Verification of depletion capability of OpenMC using VERA depletion benchmark43
Low intensity radiation image restoration method based on Bayesian maximum posterior framework42
Editorial Board41
Sodium dynamic behavior simulation and analysis under whole large leakage sodium-water reaction accident process41
A low order MOC-based synthetic acceleration scheme of the MOC neutron transport method for molten salt reactors41
Application of risk informed safety margin characterization to the analysis of a pressurized water reactor40
Groundwater path radiological impact assessment for the derivation of specific clearance levels for landfill disposed waste at Ignalina NPP39
Editorial Board38
Experimental study on the influence of drainage tank structure on separation performance of vertical corrugated plate dryer in PWR38
Modelling of the expansion phase of Sodium fast reactor severe accident38
Angular distribution uncertainty influence in a large sodium-cooled fast reactor with mixed-oxide fuel36
Thermal-hydraulic analysis of a 19-rod bundle LBE cooled fuel assembly with non-uniform rods power distribution by numerical simulation36
Development and verification of the hexagonal core simulation capability of the NECP-X code36
New approach to find the equilibrium cycle in PWR reactors using genetic algorithms35
Time-dependent leakage model for the identification of defective fuel assemblies of VVER-type nuclear reactors, part 1: Theory35
Development and validation of NECP-SARAX: An advanced neutron analysis code system for accelerator-driven subcritical systems34
Climate resilience analysis of nuclear energy by big data associated with Internet of Things (IoT)34
Lubrication performance analysis of Lead-Bismuth Internal-Feedback bearings in the nuclear main pump system33
0.28624606132507