OOIR: Observatory of International Research

Papers

(The H4-Index of Journal of Nuclear Materials is 30. 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 2022-05-01 to 2026-05-01.)

Article	Citations
Impact of anisotropic grain microstructure on the fracture-mechanical properties of ITER grade tungsten plate	263
Editorial Board	129
Quantitative in-situ investigation of dislocation loop motion in Fe9Cr1.5W ferritic/martensitic steel under the coupling effects of constant stress and irradiation	76
Editorial Board	61
Finite element analysis of the stress state and fracture in the TRISO-particle buffer layer	58
The incorporation of xenon at point defects and bubbles in uranium mononitride	57
Ductility evaluation of nitrided Zircaloy-4 cladding by ring compression testing	56
Uranium–plutonium–oxygen phase diagram: Investigating the solvus of fluorite's exsolution	56
Molecular dynamics investigation of dislocation-hydrogen/helium interactions in tungsten	53
A comprehensive atomistic investigation on the cascade induced helium bubble motion in bcc iron for neutron irradiated RAFM steels	51
Corrosion behavior of a series of combinatorial physical vapor deposition coatings on SiC in a simulated boiling water reactor environment	49
Effect of thermal oxidation on helium implanted pure iron	48
Radial hydride fraction with various rod internal pressures and hydrogen contents for Zr-Nb alloy cladding tube	47
Development of an image analysis code for hydrided Zircaloy using Dijkstra's algorithm and sensitivity analysis of radial hydride continuous path	46
Inter-diffusion of nitrogen and helium in IG-110 nuclear graphite	44
Evolution of IFMIF-DONES' heart: System overview of the Test Cell	42
Anisotropy study of hydrogen diffusion along different directions of Zr-2.5%Nb alloy pressure tube using neutron imaging	40
Characterization of modeling and experimental data inconsistencies from burst testing for high-burnup commercial fuel rod applications	40
Crud deposition behavior on zirconium alloy fuel cladding in high-temperature pressurized water environments	39
Effect of transmutation and active elements on the surface stability of silicon carbide	37
Faulted and Perfect Loop Evolution in Single Crystal Thorium Dioxide under High-Temperature Proton Irradiation	36
Determining the diffusion behavior of point defects in zirconium by a multiscale modelling approach	36
Raman spectroscopy of uranium nitride kernels	35
Tritium release performance of centrifugally granulated Li2TiO3 pebbles	34
The shear stress required for the splitting of a helical dislocation into a prismatic dislocation loop and a screw dislocation in alpha-iron	34

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]	33
Crack self-healing by high-temperature annealing of a 90W7Ni3Fe tungsten heavy alloy	32
Effect of Re aggregation doping configurations on the thermal and mechanical properties of W-Re alloys: A molecular dynamics study	31
Vacancy accumulation mechanism at iron grain boundaries: The influence of grain boundary character and its coupling with grain size	31
Experimental investigation of Kr diffusion in UO2+: Slight deviations from stoichiometry, significant effects on diffusion kinetics and mechanisms	30
Focused Ion Beam induced hydride formation does not affect Fe, Ni, Cr-clusters in irradiated Zircaloy-2	30
Tungsten fiber-reinforced tungsten composites and their thermal stability	30