OOIR: Observatory of International Research

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 2021-11-01 to 2025-11-01.)

Article	Citations
Editorial Board	224
Monte Carlo transport correction for graphite-moderated nuclear reactors using the Cumulative Migration Method	133
Online inventory modeling of a CANDU-6 reactor for nuclear forensic applications	67
A comparative study of machine learning approaches for identification of perturbed fuel assemblies in WWER-type nuclear reactors	60
Parametric investigation of mercury cell electrolysis for isotopic separation of Li using coupled numerical methods	58
Radiation survey for Taiwan research reactor vessel	55
Impact of experimental effects on a resolved resonance evaluation for practical applications	53
Editorial Board	52
A parametric statistical inference measure for input-based uncertainty quantification in BEPU analysis	49
Benchmarking a point reactor kinetics method with delayed neutron precursors transport using data from molten salt reactor experiment	44
Innovative control mechanism for research and test reactors using mandrel-shaped control rods	43
Variable universe fuzzy control of once-through steam generator feedwater	42
Development of lumped-parameter models for debris bed remelting analysis	42
Low intensity radiation image restoration method based on Bayesian maximum posterior framework	41
Climate resilience analysis of nuclear energy by big data associated with Internet of Things (IoT)	40
Evaluation of the fitting-based reactivity-equivalent physical transformation method for double heterogeneity phenomena of plate-type fuel in pressurized water reactors	38
Influence of PCHE size and types on thermodynamic and economic performance of supercritical carbon dioxide Brayton cycle for small modular reactors and its optimization	38
A molten salt test loop for component and instrumentation testing	36
Digital-twin-based improvements to diagnosis, prognosis, strategy assessment, and discrepancy checking in a nearly autonomous management and control system	36
Study on neutron shielding performance of hot cell shielding door for nuclear power plant	36
Verification of depletion capability of OpenMC using VERA depletion benchmark	36
A state-of-the-art review on performance measurement petri net models for safety critical systems of NPP	35
An analytic approach to the design of passively safe lead-cooled reactors	34
A semi-implicit Chord Length Sampling method for dispersion fuel analysis	33
Sodium dynamic behavior simulation and analysis under whole large leakage sodium-water reaction accident process	32

Thermal-hydraulic analysis of a 19-rod bundle LBE cooled fuel assembly with non-uniform rods power distribution by numerical simulation	32
General solution of Bateman equations using Cauchy products and the Theory of Divided Differences	31
TRACE system code benchmark of Station Blackout of a NuScale-like reactor and comparison with NuScale simulator	31
Global Sensitivity Analysis for Segmented Inverse Uncertainty Quantification in the Safety Analysis of Nuclear Power Plants	30
Research on sensor fault tolerance technology in nuclear power plant control system	30
Application of risk informed safety margin characterization to the analysis of a pressurized water reactor	30
Study on the mechanical behavior of penetrations in floating nuclear power plants under ocean swing load	30