OOIR: Observatory of International Research

Papers

(The H4-Index of Progress in Nuclear Energy is 37. 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 2022-08-01 to 2026-08-01.)

Article	Citations
Development of a numerical model for disassembly phase of hypothetical core disruptive accident and application to a medium-sized mixed oxide fuelled fast reactor	211
Study of fluid-elastic instability of the spatially bent tube structure in fast reactor intermediate heat exchanger	178
An evaluation of techniques for the measurement of fission gas in irradiated fuel rods	163
Research and development of the neutron-photon coupled transport method in the fast reactor code system MOSASAUR	160
Primary study on the recovery of lead from waste flexible X/Gamma ray shielding materials using pyrolysis	137
A comparison study on the burnup of HTR-10 fuels using radiometric and mass spectrometric methods	124
Improvement on Fourier fundamental mode coefficient for Monte Carlo criticality calculations	75
Editorial Board	72
Potential flame retardancy of high-density polyethylene (HDPE) composite for possible use as a radiation shield	68
Significant improvement in the gamma ray attenuation properties of bismuth tellurite glass using molybdenum oxide reinforcement	68
Influence of throat and diverging section on the performance of venturi scrubber by using computational fluid dynamics	66
A non-destructive model for thermal-hydraulics of wire-wrapped rod bundle and wire-rod contact corner microscopic behavior	56
Analysis schemes to evaluate HELB-induced blast waves	54
Numerical study on the interface debonding effect on FCM fuel behavior	53
Calculation acceleration for fuel cycle simulation of molten salt reactor based on multi-group cross section method	53
Theoretical study on pressure oscillation dominant frequency of bubbles submerged jet under rolling condition	52
Post-irradiation examination of silicide fuel (U3Si2-Al) with 4.8 gU/cm3 for RSG-GAS	51
Effect of tip injection on performance of high-load helium compressor cascade in high temperature gas-cooled reactor	50
Neutron and gamma radiation effects on thermal storage properties of polyethylene wax	50
Detail CFD simulation of the integrated reactor pressure vessel of SMART	48
Multi-step time series prediction for nuclear power plants based on variational mode decomposition and gated recurrent units	44
Elucidating the influences of strontium (II) oxides in TeO2–B2O3–BaO: Fabrication, Raman spectroscopy, and γ-ray protection properties for the novel high-density glasses	44
Surrogate modeling of heat transfer under flow fluctuation conditions using Fourier Basis-Deep Operator Network with uncertainty quantification	43
Upgrade of FROBA code to derive new insights in fuel performance of Lead-Bismuth Eutectic Cooled Fast Reactor	43
Bus based emergency evacuation organization strategy of nuclear power plant planning restricted area	43

Static output feedback H∞43
Fault diagnosis in reactor coolant pump with an automatic CNN-based mixed model	43
Improved dynamic fuzzy neural network-based power control for the load following of lead-cooled fast reactor	42
Two-group approach to develop drift-flux model for downward dispersed two-phase flows	42
Development and application of a multi-scale coupling model for dispersion plate-type fuel	41
Stator current-based soft sensing for blade damage diagnosis in centrifugal pumps using ensemble learning	41
CFD analysis of heat transfer in homogeneous and stratified corium pools for In-Vessel Retention assessment	40
Comprehensive analysis of the effects of Mo and Co on the synthesis, structural, and radiation-shielding properties of TiO2 based composites	40
Evaluation and optimization of efficiency, mass and economics of megawatt-scale space gas-cooled nuclear reactor system	39
Performance analysis of indirect contact heat pipe radiator for space nuclear power system	38
Accident event progression, gaps, and key performance indicators for steam generator tube rupture events in water-cooled SMRs: A review	38
Numerical study of forced circulation and natural circulation transition characteristics of a small modular reactor equipped with helical-coiled steam generators	37