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 2021-10-01 to 2025-10-01.)

Article	Citations
Study on transient characteristics for bypass valve regulation and load rejection of microreactor with helium Brayton cycle	300
Numerical study of forced circulation and natural circulation transition characteristics of a small modular reactor equipped with helical-coiled steam generators	232
Post-irradiation examination of silicide fuel (U3Si2-Al) with 4.8 gU/cm3 for RSG-GAS	192
Development of a numerical model for disassembly phase of hypothetical core disruptive accident and application to a medium-sized mixed oxide fuelled fast reactor	150
Study of fluid-elastic instability of the spatially bent tube structure in fast reactor intermediate heat exchanger	119
Analysis schemes to evaluate HELB-induced blast waves	111
Theoretical study on pressure oscillation dominant frequency of bubbles submerged jet under rolling condition	110
Neutron and gamma radiation effects on thermal storage properties of polyethylene wax	110
U(VI) speciation studies by Raman spectroscopy technique in the production of nuclear fuel	101
An evaluation of techniques for the measurement of fission gas in irradiated fuel rods	90
A comparison study on the burnup of HTR-10 fuels using radiometric and mass spectrometric methods	87
Detail CFD simulation of the integrated reactor pressure vessel of SMART	87
A non-destructive model for thermal-hydraulics of wire-wrapped rod bundle and wire-rod contact corner microscopic behavior	77
Improvement on Fourier fundamental mode coefficient for Monte Carlo criticality calculations	76
Self-sustainability and energy-balance in a fast Fusion–Fission Hybrid Reactor (FFHR) based on Dense Plasma Focus (DPF) and multiplicative cascade	75
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	74
Research on equipment survivability assessment in severe accidents for CANDU6	60
Prediction of 3D natural convection heat transfer characteristics in a shallow enclosure with experimental data	58
Comprehensive analysis of the effects of Mo and Co on the synthesis, structural, and radiation-shielding properties of TiO2 based composites	53
Influence of throat and diverging section on the performance of venturi scrubber by using computational fluid dynamics	52
Gamma radiation shielding performance of CuxAg(1-x)-alloys: Experimental, theoretical and simulation results	49
Primary study on the recovery of lead from waste flexible X/Gamma ray shielding materials using pyrolysis	48
Potential flame retardancy of high-density polyethylene (HDPE) composite for possible use as a radiation shield	48
Accident event progression, gaps, and key performance indicators for steam generator tube rupture events in water-cooled SMRs: A review	45
Load-following control of a nuclear reactor using optimized FOPID controller based on the two-point fractional neutron kinetics model considering reactivity feedback effects	45

Gamma radiation attenuation characteristics of composites based on polyimide track membranes filled with nanodispersed Pb	45
Editorial Board	44
Bus based emergency evacuation organization strategy of nuclear power plant planning restricted area	42
Uncertainty propagation of prompt fission neutron spectrum for physics analysis of fast and thermal reactors	41
Weierstrass function methodology for uncertainty analysis of random media criticality with spectrum range control	40
CFD simulation on sub-channel blockage in the fuel plate of RSG-GAS reactor	40
Assessment of thermal shock resistance of refractory magnesia lining under simulated core melt impingement for application to SFR core catcher	40
Eigenvalues of the neutron transport equation in X–	39
Static output feedback H∞39
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	39
Numerical study on the interface debonding effect on FCM fuel behavior	39
Calculation acceleration for fuel cycle simulation of molten salt reactor based on multi-group cross section method	38
Surrogate modeling of heat transfer under flow fluctuation conditions using Fourier Basis-Deep Operator Network with uncertainty quantification	37
Effect of tip injection on performance of high-load helium compressor cascade in high temperature gas-cooled reactor	37