OOIR: Observatory of International Research

Papers

(The H4-Index of Progress in Nuclear Energy is 36. 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 2021-09-01 to 2025-09-01.)

Article	Citations
Editorial Board	295
Research on equipment survivability assessment in severe accidents for CANDU6	221
Influence of throat and diverging section on the performance of venturi scrubber by using computational fluid dynamics	190
Study on transient characteristics for bypass valve regulation and load rejection of microreactor with helium Brayton cycle	148
Calculation acceleration for fuel cycle simulation of molten salt reactor based on multi-group cross section method	115
A non-destructive model for thermal-hydraulics of wire-wrapped rod bundle and wire-rod contact corner microscopic behavior	110
Accident event progression, gaps, and key performance indicators for steam generator tube rupture events in water-cooled SMRs: A review	106
Numerical study of forced circulation and natural circulation transition characteristics of a small modular reactor equipped with helical-coiled steam generators	104
Post-irradiation examination of silicide fuel (U3Si2-Al) with 4.8 gU/cm3 for RSG-GAS	100
Development of a numerical model for disassembly phase of hypothetical core disruptive accident and application to a medium-sized mixed oxide fuelled fast reactor	89
Study of fluid-elastic instability of the spatially bent tube structure in fast reactor intermediate heat exchanger	86
Analysis schemes to evaluate HELB-induced blast waves	84
Detail CFD simulation of the integrated reactor pressure vessel of SMART	76
Weierstrass function methodology for uncertainty analysis of random media criticality with spectrum range control	74
Theoretical study on pressure oscillation dominant frequency of bubbles submerged jet under rolling condition	74
A comparison study on the burnup of HTR-10 fuels using radiometric and mass spectrometric methods	70
Improvement on Fourier fundamental mode coefficient for Monte Carlo criticality calculations	60
Neutron and gamma radiation effects on thermal storage properties of polyethylene wax	57
Load-following control of a nuclear reactor using optimized FOPID controller based on the two-point fractional neutron kinetics model considering reactivity feedback effects	53
Static output feedbackH∞	52
Effect of tip injection on performance of high-load helium compressor cascade in high temperature gas-cooled reactor	47
Numerical study on the interface debonding effect on FCM fuel behavior	46
Gamma radiation attenuation characteristics of composites based on polyimide track membranes filled with nanodispersed Pb	45
Physics-Informed Neural Networks for the safety analysis of nuclear reactors	44
An evaluation of techniques for the measurement of fission gas in irradiated fuel rods	43

Eigenvalues of the neutron transport equation in X–	43
CFD simulation on sub-channel blockage in the fuel plate of RSG-GAS reactor	41
Assessment of thermal shock resistance of refractory magnesia lining under simulated core melt impingement for application to SFR core catcher	40
Qualification of RELAP5-3D code condensation model against full-scale PERSEO Test 9	40
Application of response surface methodology for modeling and optimization of the extraction and separation of Se(IV) and Te(IV) from nitric acid solution by Cyanex 301 extractant	40
Improved dynamic fuzzy neural network-based power control for the load following of lead-cooled fast reactor	39
Bus based emergency evacuation organization strategy of nuclear power plant planning restricted area	39
Primary study on the recovery of lead from waste flexible X/Gamma ray shielding materials using pyrolysis	38
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	37
Potential flame retardancy of high-density polyethylene (HDPE) composite for possible use as a radiation shield	37
Prediction of 3D natural convection heat transfer characteristics in a shallow enclosure with experimental data	36
Performance analysis of indirect contact heat pipe radiator for space nuclear power system	36