OOIR: Observatory of International Research

Papers

(The H4-Index of Journal of Nuclear Materials is 32. 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
Positron annihilation study of the reactor pressure vessel model steels irradiated in the high flux reactor	172
Effect of Re aggregation doping configurations on the thermal and mechanical properties of W-Re alloys: A molecular dynamics study	73
Radial hydride fraction with various rod internal pressures and hydrogen contents for Zr-Nb alloy cladding tube	60
Development of an image analysis code for hydrided Zircaloy using Dijkstra's algorithm and sensitivity analysis of radial hydride continuous path	57
Editorial Board	56
Characterization of modeling and experimental data inconsistencies from burst testing for high-burnup commercial fuel rod applications	56
Raman spectroscopy of uranium nitride kernels	55
Effect of thermal oxidation on helium implanted pure iron	54
Corrigendum to “Experimental assessment of thermodynamic stability and nucleation of NiO in liquid lead-bismuth eutectic for MYRRHA” [Journal of Nuclear Materials 603 (2025) 155404]	54
Determining the diffusion behavior of point defects in zirconium by a multiscale modelling approach	53
Predictions of the full-life pressurised water stress corrosion cracking behaviour of 690 weld joints	51
He nanobubble driven W surface growth during low-energy He ion irradiations	50
Quantitative in-situ investigation of dislocation loop motion in Fe9Cr1.5W ferritic/martensitic steel under the coupling effects of constant stress and irradiation	48
Calculation of grain boundary diffusion coefficients in γU-Mo using atomistic simulations	45
Atomistic modelling of iodine-oxygen interactions in strained sub-oxides of zirconium	44
Dose-dependent strain localization and embrittlement in ferritic materials: A predictive approach based on sub-grain plasticity modelling	44
On the influence of microstructure on the neutron irradiation response of HIPed SA508 steel for nuclear applications	43
The vacancy-mediated diffusion of transition metal solutes in tungsten: Atomic Kinetic Monte Carlo simulations	41
Burst characteristics of advanced accident-tolerant FeCrAl cladding under temperature transient testing	40
Effect of point defects on water adsorption on the ThO2{111} surface: A first-principles computational study	39
In-situ ion irradiation study of alloy 709 stainless steels with different processing histories	39
Demonstration of an integrated-heating load frame for quantitatively assessing microscale tensile properties of copper and Zircaloy-2	39
Experimental investigation of Kr diffusion in UO2+: Slight deviations from stoichiometry, significant effects on diffusion kinetics and mechanisms	37
Systematic experimental and model-based evaluation of the synergistic effects of alloy composition and damage rate on the formation of Cr-rich precipitates in Fe–Cr–Al alloys under ion irradiation	35
Anisotropy study of hydrogen diffusion along different directions of Zr-2.5%Nb alloy pressure tube using neutron imaging	35

Effect of scratch depth on high cycle fatigue behavior of Alloy 690TT stream generator tube	34
Crack self-healing by high-temperature annealing of a 90W7Ni3Fe tungsten heavy alloy	34
Dislocation loop coarsening and shape evolution upon annealing neutron-irradiated RAFM steel	33
Dose and dose rate dependence of precipitation in a series of surveillance RPV steels under ion and neutron irradiation	32
Annealing of the Raman defect peaks in He-implanted UO2	32
Uranium–plutonium–oxygen phase diagram: Investigating the solvus of fluorite's exsolution	32
Understanding the local thermal conductivity evolution of neutron irradiated U3Si2 dispersion fuel via state-of-the-art thermo-reflectance measurements	32