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 2021-05-01 to 2025-05-01.)

Article	Citations
Significant improvement in the gamma ray attenuation properties of bismuth tellurite glass using molybdenum oxide reinforcement	280
Assessment of thermal shock resistance of refractory magnesia lining under simulated core melt impingement for application to SFR core catcher	182
CFD simulation on sub-channel blockage in the fuel plate of RSG-GAS reactor	176
Editorial Board	141
Self-sustainability and energy-balance in a fast Fusion–Fission Hybrid Reactor (FFHR) based on Dense Plasma Focus (DPF) and multiplicative cascade	107
Research on equipment survivability assessment in severe accidents for CANDU6	101
Computational fluid dynamics analysis of buoyancy-aided turbulent mixed convection inside a heated vertical rectangular duct	100
Influence of throat and diverging section on the performance of venturi scrubber by using computational fluid dynamics	95
Study on transient characteristics for bypass valve regulation and load rejection of microreactor with helium Brayton cycle	93
Calculation acceleration for fuel cycle simulation of molten salt reactor based on multi-group cross section method	92
A non-destructive model for thermal-hydraulics of wire-wrapped rod bundle and wire-rod contact corner microscopic behavior	85
Fault diagnosis in reactor coolant pump with an automatic CNN-based mixed model	80
Improved dynamic fuzzy neural network-based power control for the load following of lead-cooled fast reactor	79
Numerical study of forced circulation and natural circulation transition characteristics of a small modular reactor equipped with helical-coiled steam generators	74
Development of a numerical model for disassembly phase of hypothetical core disruptive accident and application to a medium-sized mixed oxide fuelled fast reactor	73
Post-irradiation examination of silicide fuel (U3Si2-Al) with 4.8 gU/cm3 for RSG-GAS	73
Study of fluid-elastic instability of the spatially bent tube structure in fast reactor intermediate heat exchanger	69
Analysis schemes to evaluate HELB-induced blast waves	68
Primary study on the recovery of lead from waste flexible X/Gamma ray shielding materials using pyrolysis	58
Detail CFD simulation of the integrated reactor pressure vessel of SMART	52
Theoretical study on pressure oscillation dominant frequency of bubbles submerged jet under rolling condition	51
Research and development of the neutron-photon coupled transport method in the fast reactor code system MOSASAUR	50
Weierstrass function methodology for uncertainty analysis of random media criticality with spectrum range control	47
Neutron and gamma radiation effects on thermal storage properties of polyethylene wax	47
Improvement on Fourier fundamental mode coefficient for Monte Carlo criticality calculations	47

A comparison study on the burnup of HTR-10 fuels using radiometric and mass spectrometric methods	47
Eigenvalues of the neutron transport equation in X–	41
Effect of tip injection on performance of high-load helium compressor cascade in high temperature gas-cooled reactor	40
Load-following control of a nuclear reactor using optimized FOPID controller based on the two-point fractional neutron kinetics model considering reactivity feedback effects	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	38
Potential flame retardancy of high-density polyethylene (HDPE) composite for possible use as a radiation shield	38
Application of Hazard and Operability Technique to Level 1 Probabilistic Safety Assessment of Thai Research Reactor-1/Modification 1: Internal Events and Human Errors	37
Prediction of 3D natural convection heat transfer characteristics in a shallow enclosure with experimental data	37
Gamma radiation attenuation characteristics of composites based on polyimide track membranes filled with nanodispersed Pb	36
Finding a suitable fuel type for the disposal of the accumulated minor actinides in the spent nuclear fuel in PWR	36
Numerical study on the interface debonding effect on FCM fuel behavior	36