OOIR: Observatory of International Research

Papers

(The H4-Index of Annals of Nuclear Energy is 31. 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 2021-07-01 to 2025-07-01.)

Article	Citations
Visualization experimental investigation on flow boiling and critical heat flux characteristics of helical fuel	177
A novel approach for software reliability analysis of digital instrumentation and control systems in nuclear power plants	124
Modelling of the expansion phase of Sodium fast reactor severe accident	65
Assessment of WWER 1000 core degradation in a severe accident condition induced by MB-LOCA	56
Impact of experimental effects on a resolved resonance evaluation for practical applications	55
A low order MOC-based synthetic acceleration scheme of the MOC neutron transport method for molten salt reactors	55
An investigation of structural strength of PWR fuel assembly spacer grid with fuel rod clad	49
Design of temperature controlled instrumented irradiation capsule for irradiation experiments in FBTR	49
Monte Carlo transport correction for graphite-moderated nuclear reactors using the Cumulative Migration Method	48
Online inventory modeling of a CANDU-6 reactor for nuclear forensic applications	47
Vectorial finite element method for neutron transport solving with preconditioning GMRES acceleration	46
The gamma deposition matrix method for gamma heating calculations for LWRs	43
Study on neutron shielding performance of hot cell shielding door for nuclear power plant	41
Editorial Board	40
Experimental analysis of boron dilution transient flow mixing characteristics based on planar laser induced fluorescence measurement	39
Technical Note: Development of a generalized source model for flux estimation in nuclear reactors	38
Experimental study on the influence of drainage tank structure on separation performance of vertical corrugated plate dryer in PWR	37
Editorial Board	37
Radiation survey for Taiwan research reactor vessel	36
Evaluation of the fitting-based reactivity-equivalent physical transformation method for double heterogeneity phenomena of plate-type fuel in pressurized water reactors	35
Effect of bubble entrainment on thermal–hydraulic performance of LBE-cooled wire-wrapped rod bundles	35
Study on the mechanical behavior of penetrations in floating nuclear power plants under ocean swing load	35
A parametric statistical inference measure for input-based uncertainty quantification in BEPU analysis	34
One dimensional analytical model considering end effects for analysis of electromagnetic pressure characteristics of annular linear induction electromagnetic pump	33
Prediction of stress-fatigue life on the impeller of the reactor coolant pump based on fluid-thermal-structure interaction method	33

Development of lumped-parameter models for debris bed remelting analysis	33
TRACE system code benchmark of Station Blackout of a NuScale-like reactor and comparison with NuScale simulator	32
Innovative control mechanism for research and test reactors using mandrel-shaped control rods	32
Benchmarking a point reactor kinetics method with delayed neutron precursors transport using data from molten salt reactor experiment	32
Development and verification of the hexagonal core simulation capability of the NECP-X code	31
Verification of depletion capability of OpenMC using VERA depletion benchmark	31