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 2021-07-01 to 2025-07-01.)

Article	Citations
Editorial Board	290
Research on equipment survivability assessment in severe accidents for CANDU6	202
Computational fluid dynamics analysis of buoyancy-aided turbulent mixed convection inside a heated vertical rectangular duct	181
Influence of throat and diverging section on the performance of venturi scrubber by using computational fluid dynamics	144
Study on transient characteristics for bypass valve regulation and load rejection of microreactor with helium Brayton cycle	120
Calculation acceleration for fuel cycle simulation of molten salt reactor based on multi-group cross section method	108
A non-destructive model for thermal-hydraulics of wire-wrapped rod bundle and wire-rod contact corner microscopic behavior	107
Accident event progression, gaps, and key performance indicators for steam generator tube rupture events in water-cooled SMRs: A review	98
Research and development of the neutron-photon coupled transport method in the fast reactor code system MOSASAUR	97
Gamma radiation shielding performance of CuxAg(1-x)-alloys: Experimental, theoretical and simulation results	94
Fault diagnosis in reactor coolant pump with an automatic CNN-based mixed model	93
Numerical study of forced circulation and natural circulation transition characteristics of a small modular reactor equipped with helical-coiled steam generators	86
Post-irradiation examination of silicide fuel (U3Si2-Al) with 4.8 gU/cm3 for RSG-GAS	82
Development of a numerical model for disassembly phase of hypothetical core disruptive accident and application to a medium-sized mixed oxide fuelled fast reactor	82
Study of fluid-elastic instability of the spatially bent tube structure in fast reactor intermediate heat exchanger	78
Analysis schemes to evaluate HELB-induced blast waves	76
Detail CFD simulation of the integrated reactor pressure vessel of SMART	73
Theoretical study on pressure oscillation dominant frequency of bubbles submerged jet under rolling condition	71
Weierstrass function methodology for uncertainty analysis of random media criticality with spectrum range control	64
A comparison study on the burnup of HTR-10 fuels using radiometric and mass spectrometric methods	55
Improvement on Fourier fundamental mode coefficient for Monte Carlo criticality calculations	54
Neutron and gamma radiation effects on thermal storage properties of polyethylene wax	53
Numerical study on the interface debonding effect on FCM fuel behavior	50
Gamma radiation attenuation characteristics of composites based on polyimide track membranes filled with nanodispersed Pb	49
Physics-Informed Neural Networks for the safety analysis of nuclear reactors	45

Eigenvalues of the neutron transport equation in X–	44
An evaluation of techniques for the measurement of fission gas in irradiated fuel rods	43
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	42
CFD simulation on sub-channel blockage in the fuel plate of RSG-GAS reactor	42
Self-sustainability and energy-balance in a fast Fusion–Fission Hybrid Reactor (FFHR) based on Dense Plasma Focus (DPF) and multiplicative cascade	41
Marvin: A parallel three-dimensional transport code based on the discrete ordinates method for reactor shielding calculations	38
Assessment of thermal shock resistance of refractory magnesia lining under simulated core melt impingement for application to SFR core catcher	38
Effect of tip injection on performance of high-load helium compressor cascade in high temperature gas-cooled reactor	38
Qualification of RELAP5-3D code condensation model against full-scale PERSEO Test 9	38
Evaluating the impact of airborne radionuclides caused by the Fukushima nuclear accident on China based on global atmospheric dispersion	37
Load-following control of a nuclear reactor using optimized FOPID controller based on the two-point fractional neutron kinetics model considering reactivity feedback effects	37
Improved dynamic fuzzy neural network-based power control for the load following of lead-cooled fast reactor	36
Static output feedbackH∞	36
Primary study on the recovery of lead from waste flexible X/Gamma ray shielding materials using pyrolysis	36