OOIR: Observatory of International Research

Papers

(The H4-Index of Progress in Nuclear Energy is 35. 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 2021-06-01 to 2025-06-01.)

Article	Citations
Editorial Board	284
Research on equipment survivability assessment in severe accidents for CANDU6	188
Computational fluid dynamics analysis of buoyancy-aided turbulent mixed convection inside a heated vertical rectangular duct	177
Influence of throat and diverging section on the performance of venturi scrubber by using computational fluid dynamics	143
Study on transient characteristics for bypass valve regulation and load rejection of microreactor with helium Brayton cycle	115
Calculation acceleration for fuel cycle simulation of molten salt reactor based on multi-group cross section method	105
A non-destructive model for thermal-hydraulics of wire-wrapped rod bundle and wire-rod contact corner microscopic behavior	103
Numerical study of forced circulation and natural circulation transition characteristics of a small modular reactor equipped with helical-coiled steam generators	96
Post-irradiation examination of silicide fuel (U3Si2-Al) with 4.8 gU/cm3 for RSG-GAS	96
Development of a numerical model for disassembly phase of hypothetical core disruptive accident and application to a medium-sized mixed oxide fuelled fast reactor	92
Study of fluid-elastic instability of the spatially bent tube structure in fast reactor intermediate heat exchanger	88
Analysis schemes to evaluate HELB-induced blast waves	83
Detail CFD simulation of the integrated reactor pressure vessel of SMART	80
Theoretical study on pressure oscillation dominant frequency of bubbles submerged jet under rolling condition	80
Research and development of the neutron-photon coupled transport method in the fast reactor code system MOSASAUR	74
Weierstrass function methodology for uncertainty analysis of random media criticality with spectrum range control	73
A comparison study on the burnup of HTR-10 fuels using radiometric and mass spectrometric methods	71
Improvement on Fourier fundamental mode coefficient for Monte Carlo criticality calculations	70
Neutron and gamma radiation effects on thermal storage properties of polyethylene wax	61
Effect of tip injection on performance of high-load helium compressor cascade in high temperature gas-cooled reactor	53
Numerical study on the interface debonding effect on FCM fuel behavior	52
Load-following control of a nuclear reactor using optimized FOPID controller based on the two-point fractional neutron kinetics model considering reactivity feedback effects	52
Gamma radiation attenuation characteristics of composites based on polyimide track membranes filled with nanodispersed Pb	48
Accident event progression, gaps, and key performance indicators for steam generator tube rupture events in water-cooled SMRs: A review	48
Uncertainty propagation of prompt fission neutron spectrum for physics analysis of fast and thermal reactors	43

Eigenvalues of the neutron transport equation in X–	42
Static output feedbackH∞	41
An evaluation of techniques for the measurement of fission gas in irradiated fuel rods	40
Significant improvement in the gamma ray attenuation properties of bismuth tellurite glass using molybdenum oxide reinforcement	40
CFD simulation on sub-channel blockage in the fuel plate of RSG-GAS reactor	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	38
Self-sustainability and energy-balance in a fast Fusion–Fission Hybrid Reactor (FFHR) based on Dense Plasma Focus (DPF) and multiplicative cascade	38
Assessment of thermal shock resistance of refractory magnesia lining under simulated core melt impingement for application to SFR core catcher	37
Qualification of RELAP5-3D code condensation model against full-scale PERSEO Test 9	37
Gamma radiation shielding performance of CuxAg(1-x)-alloys: Experimental, theoretical and simulation results	36
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	35
Potential flame retardancy of high-density polyethylene (HDPE) composite for possible use as a radiation shield	35