Annals of Nuclear Energy

Papers
(The H4-Index of Annals of Nuclear Energy is 30. 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 2021-06-01 to 2025-06-01.)
ArticleCitations
Visualization experimental investigation on flow boiling and critical heat flux characteristics of helical fuel163
A novel approach for software reliability analysis of digital instrumentation and control systems in nuclear power plants122
Modelling of the expansion phase of Sodium fast reactor severe accident64
Assessment of WWER 1000 core degradation in a severe accident condition induced by MB-LOCA55
Development and verification of the hexagonal core simulation capability of the NECP-X code52
A low order MOC-based synthetic acceleration scheme of the MOC neutron transport method for molten salt reactors51
Design of temperature controlled instrumented irradiation capsule for irradiation experiments in FBTR47
Impact of experimental effects on a resolved resonance evaluation for practical applications47
An investigation of structural strength of PWR fuel assembly spacer grid with fuel rod clad46
Monte Carlo transport correction for graphite-moderated nuclear reactors using the Cumulative Migration Method44
Online inventory modeling of a CANDU-6 reactor for nuclear forensic applications43
Rasterized coarse mesh finite difference acceleration on method of characteristics for a reactor core with a generalized boundary41
Vectorial finite element method for neutron transport solving with preconditioning GMRES acceleration41
The gamma deposition matrix method for gamma heating calculations for LWRs39
Study on neutron shielding performance of hot cell shielding door for nuclear power plant38
Experimental analysis of boron dilution transient flow mixing characteristics based on planar laser induced fluorescence measurement36
Editorial Board36
Technical Note: Development of a generalized source model for flux estimation in nuclear reactors35
Editorial Board34
Uncertainty analysis of source term and off-site consequence for WH600 using MELCOR and WinMACCS34
Experimental study on the influence of drainage tank structure on separation performance of vertical corrugated plate dryer in PWR34
Radiation survey for Taiwan research reactor vessel33
Variable universe fuzzy control of once-through steam generator feedwater32
Study on the mechanical behavior of penetrations in floating nuclear power plants under ocean swing load32
Evaluation of the fitting-based reactivity-equivalent physical transformation method for double heterogeneity phenomena of plate-type fuel in pressurized water reactors32
Effect of bubble entrainment on thermal–hydraulic performance of LBE-cooled wire-wrapped rod bundles31
Low intensity radiation image restoration method based on Bayesian maximum posterior framework30
Corrigendum to ‘Integral transport in a three region sphere with associated benchmark problems’ [Ann. Nucl. Energy 32 (2005) 1047–1067]30
A parametric statistical inference measure for input-based uncertainty quantification in BEPU analysis30
Dynamic mode decomposition for subcriticality measurement using measured data at single location30
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