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 2022-06-01 to 2026-06-01.)

Article	Citations
High-fidelity microreactor load follow simulations with model predictive control	344
Development of a numerical model for disassembly phase of hypothetical core disruptive accident and application to a medium-sized mixed oxide fuelled fast reactor	207
Study of fluid-elastic instability of the spatially bent tube structure in fast reactor intermediate heat exchanger	172
An evaluation of techniques for the measurement of fission gas in irradiated fuel rods	156
Research and development of the neutron-photon coupled transport method in the fast reactor code system MOSASAUR	155
Study on transient characteristics for bypass valve regulation and load rejection of microreactor with helium Brayton cycle	149
Performance analysis of indirect contact heat pipe radiator for space nuclear power system	133
Primary study on the recovery of lead from waste flexible X/Gamma ray shielding materials using pyrolysis	118
A comparison study on the burnup of HTR-10 fuels using radiometric and mass spectrometric methods	85
Improvement on Fourier fundamental mode coefficient for Monte Carlo criticality calculations	71
Research on equipment survivability assessment in severe accidents for CANDU6	70
Numerical study of forced circulation and natural circulation transition characteristics of a small modular reactor equipped with helical-coiled steam generators	63
Static output feedback H∞63
CFD simulation on sub-channel blockage in the fuel plate of RSG-GAS reactor	61
Editorial Board	54
Significant improvement in the gamma ray attenuation properties of bismuth tellurite glass using molybdenum oxide reinforcement	51
Potential flame retardancy of high-density polyethylene (HDPE) composite for possible use as a radiation shield	50
Two-group approach to develop drift-flux model for downward dispersed two-phase flows	50
Influence of throat and diverging section on the performance of venturi scrubber by using computational fluid dynamics	49
Post-irradiation examination of silicide fuel (U3Si2-Al) with 4.8 gU/cm3 for RSG-GAS	47
Assessment of thermal shock resistance of refractory magnesia lining under simulated core melt impingement for application to SFR core catcher	47
Neutron and gamma radiation effects on thermal storage properties of polyethylene wax	47
Effect of tip injection on performance of high-load helium compressor cascade in high temperature gas-cooled reactor	46
Prediction of 3D natural convection heat transfer characteristics in a shallow enclosure with experimental data	46
Detail CFD simulation of the integrated reactor pressure vessel of SMART	43

Comprehensive analysis of the effects of Mo and Co on the synthesis, structural, and radiation-shielding properties of TiO2 based composites	43
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	42
Multi-step time series prediction for nuclear power plants based on variational mode decomposition and gated recurrent units	41
Bus based emergency evacuation organization strategy of nuclear power plant planning restricted area	41
Physics-Informed Neural Networks for the safety analysis of nuclear reactors	40
Upgrade of FROBA code to derive new insights in fuel performance of Lead-Bismuth Eutectic Cooled Fast Reactor	40
Stator current-based soft sensing for blade damage diagnosis in centrifugal pumps using ensemble learning	40
A non-destructive model for thermal-hydraulics of wire-wrapped rod bundle and wire-rod contact corner microscopic behavior	38
Analysis schemes to evaluate HELB-induced blast waves	37
CFD analysis of heat transfer in homogeneous and stratified corium pools for In-Vessel Retention assessment	37
Fault diagnosis in reactor coolant pump with an automatic CNN-based mixed model	37
Numerical study on the interface debonding effect on FCM fuel behavior	37