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 2022-01-01 to 2026-01-01.)

Article	Citations
High-fidelity microreactor load follow simulations with model predictive control	317
Development of a numerical model for disassembly phase of hypothetical core disruptive accident and application to a medium-sized mixed oxide fuelled fast reactor	266
Study of fluid-elastic instability of the spatially bent tube structure in fast reactor intermediate heat exchanger	197
Analysis schemes to evaluate HELB-induced blast waves	159
Prediction of 3D natural convection heat transfer characteristics in a shallow enclosure with experimental data	132
Uncertainty propagation of prompt fission neutron spectrum for physics analysis of fast and thermal reactors	126
Eigenvalues of the neutron transport equation in X–	125
Static output feedback H∞108
Theoretical study on pressure oscillation dominant frequency of bubbles submerged jet under rolling condition	107
Primary study on the recovery of lead from waste flexible X/Gamma ray shielding materials using pyrolysis	81
A comparison study on the burnup of HTR-10 fuels using radiometric and mass spectrometric methods	79
A non-destructive model for thermal-hydraulics of wire-wrapped rod bundle and wire-rod contact corner microscopic behavior	76
Improvement on Fourier fundamental mode coefficient for Monte Carlo criticality calculations	64
Self-sustainability and energy-balance in a fast Fusion–Fission Hybrid Reactor (FFHR) based on Dense Plasma Focus (DPF) and multiplicative cascade	59
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	56
Neutron and gamma radiation effects on thermal storage properties of polyethylene wax	55
Research on equipment survivability assessment in severe accidents for CANDU6	55
Performance analysis of indirect contact heat pipe radiator for space nuclear power system	52
Potential flame retardancy of high-density polyethylene (HDPE) composite for possible use as a radiation shield	51
An evaluation of techniques for the measurement of fission gas in irradiated fuel rods	50
Stator current-based soft sensing for blade damage diagnosis in centrifugal pumps using ensemble learning	49
Numerical study on the interface debonding effect on FCM fuel behavior	46
Assessment of thermal shock resistance of refractory magnesia lining under simulated core melt impingement for application to SFR core catcher	44
Research and development of the neutron-photon coupled transport method in the fast reactor code system MOSASAUR	43
Surrogate modeling of heat transfer under flow fluctuation conditions using Fourier Basis-Deep Operator Network with uncertainty quantification	43

Weierstrass function methodology for uncertainty analysis of random media criticality with spectrum range control	43
Multi-step time series prediction for nuclear power plants based on variational mode decomposition and gated recurrent units	42
Study on transient characteristics for bypass valve regulation and load rejection of microreactor with helium Brayton cycle	41
CFD simulation on sub-channel blockage in the fuel plate of RSG-GAS reactor	41
Influence of throat and diverging section on the performance of venturi scrubber by using computational fluid dynamics	40
Numerical study of forced circulation and natural circulation transition characteristics of a small modular reactor equipped with helical-coiled steam generators	39
Significant improvement in the gamma ray attenuation properties of bismuth tellurite glass using molybdenum oxide reinforcement	38
Effect of tip injection on performance of high-load helium compressor cascade in high temperature gas-cooled reactor	38
Post-irradiation examination of silicide fuel (U3Si2-Al) with 4.8 gU/cm3 for RSG-GAS	38
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
Gamma radiation shielding performance of CuxAg(1-x)-alloys: Experimental, theoretical and simulation results	37
Detail CFD simulation of the integrated reactor pressure vessel of SMART	37