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 2021-08-01 to 2025-08-01.)

Article	Citations
A novel approach for software reliability analysis of digital instrumentation and control systems in nuclear power plants	186
Modelling of the expansion phase of Sodium fast reactor severe accident	124
Assessment of WWER 1000 core degradation in a severe accident condition induced by MB-LOCA	65
A low order MOC-based synthetic acceleration scheme of the MOC neutron transport method for molten salt reactors	57
Impact of experimental effects on a resolved resonance evaluation for practical applications	55
Design of temperature controlled instrumented irradiation capsule for irradiation experiments in FBTR	55
Monte Carlo transport correction for graphite-moderated nuclear reactors using the Cumulative Migration Method	53
Online inventory modeling of a CANDU-6 reactor for nuclear forensic applications	50
Study on neutron shielding performance of hot cell shielding door for nuclear power plant	48
The gamma deposition matrix method for gamma heating calculations for LWRs	48
Editorial Board	47
Experimental analysis of boron dilution transient flow mixing characteristics based on planar laser induced fluorescence measurement	45
Technical Note: Development of a generalized source model for flux estimation in nuclear reactors	43
Radiation survey for Taiwan research reactor vessel	40
Editorial Board	40
Experimental study on the influence of drainage tank structure on separation performance of vertical corrugated plate dryer in PWR	40
Evaluation of the fitting-based reactivity-equivalent physical transformation method for double heterogeneity phenomena of plate-type fuel in pressurized water reactors	38
Effect of bubble entrainment on thermal–hydraulic performance of LBE-cooled wire-wrapped rod bundles	37
Study on the mechanical behavior of penetrations in floating nuclear power plants under ocean swing load	37
Prediction of stress-fatigue life on the impeller of the reactor coolant pump based on fluid-thermal-structure interaction method	36
A parametric statistical inference measure for input-based uncertainty quantification in BEPU analysis	36
Development of lumped-parameter models for debris bed remelting analysis	35
Innovative control mechanism for research and test reactors using mandrel-shaped control rods	34
Benchmarking a point reactor kinetics method with delayed neutron precursors transport using data from molten salt reactor experiment	34
TRACE system code benchmark of Station Blackout of a NuScale-like reactor and comparison with NuScale simulator	34

Low intensity radiation image restoration method based on Bayesian maximum posterior framework	33
Accuracy and efficient solution of helical coiled once-through steam generator model using JFNK method	33
Preliminary conceptual design and neutroncis analysis of a heat pipe cooled traveling wave reactor	33
Development and verification of the hexagonal core simulation capability of the NECP-X code	33
Visualization experimental investigation on flow boiling and critical heat flux characteristics of helical fuel	32
Climate resilience analysis of nuclear energy by big data associated with Internet of Things (IoT)	31