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 2021-11-01 to 2025-11-01.)

Article	Citations
High-fidelity microreactor load follow simulations with model predictive control	305
Development of a numerical model for disassembly phase of hypothetical core disruptive accident and application to a medium-sized mixed oxide fuelled fast reactor	244
Study of fluid-elastic instability of the spatially bent tube structure in fast reactor intermediate heat exchanger	195
Post-irradiation examination of silicide fuel (U3Si2-Al) with 4.8 gU/cm3 for RSG-GAS	153
Analysis schemes to evaluate HELB-induced blast waves	127
Study on transient characteristics for bypass valve regulation and load rejection of microreactor with helium Brayton cycle	115
Editorial Board	113
Uncertainty propagation of prompt fission neutron spectrum for physics analysis of fast and thermal reactors	111
Weierstrass function methodology for uncertainty analysis of random media criticality with spectrum range control	103
Numerical study on the interface debonding effect on FCM fuel behavior	92
CFD simulation on sub-channel blockage in the fuel plate of RSG-GAS reactor	92
Eigenvalues of the neutron transport equation in X–	89
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	80
Calculation acceleration for fuel cycle simulation of molten salt reactor based on multi-group cross section method	78
Static output feedback H∞77
Comprehensive analysis of the effects of Mo and Co on the synthesis, structural, and radiation-shielding properties of TiO2 based composites	76
Effect of tip injection on performance of high-load helium compressor cascade in high temperature gas-cooled reactor	62
Theoretical study on pressure oscillation dominant frequency of bubbles submerged jet under rolling condition	61
Primary study on the recovery of lead from waste flexible X/Gamma ray shielding materials using pyrolysis	53
Accident event progression, gaps, and key performance indicators for steam generator tube rupture events in water-cooled SMRs: A review	51
An evaluation of techniques for the measurement of fission gas in irradiated fuel rods	50
A comparison study on the burnup of HTR-10 fuels using radiometric and mass spectrometric methods	49
Detail CFD simulation of the integrated reactor pressure vessel of SMART	48
A non-destructive model for thermal-hydraulics of wire-wrapped rod bundle and wire-rod contact corner microscopic behavior	48
Improvement on Fourier fundamental mode coefficient for Monte Carlo criticality calculations	47

Self-sustainability and energy-balance in a fast Fusion–Fission Hybrid Reactor (FFHR) based on Dense Plasma Focus (DPF) and multiplicative cascade	44
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	44
Influence of throat and diverging section on the performance of venturi scrubber by using computational fluid dynamics	42
Research on equipment survivability assessment in severe accidents for CANDU6	42
Neutron and gamma radiation effects on thermal storage properties of polyethylene wax	42
Load-following control of a nuclear reactor using optimized FOPID controller based on the two-point fractional neutron kinetics model considering reactivity feedback effects	41
U(VI) speciation studies by Raman spectroscopy technique in the production of nuclear fuel	41
Physics-Informed Neural Networks for the safety analysis of nuclear reactors	41
Prediction of 3D natural convection heat transfer characteristics in a shallow enclosure with experimental data	40
Gamma radiation shielding performance of CuxAg(1-x)-alloys: Experimental, theoretical and simulation results	40
Performance analysis of indirect contact heat pipe radiator for space nuclear power system	40
Research and development of the neutron-photon coupled transport method in the fast reactor code system MOSASAUR	37