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 2022-06-01 to 2026-06-01.)

Article	Citations
Impact of anisotropic grain microstructure on the fracture-mechanical properties of ITER grade tungsten plate	132
Editorial Board	81
Quantitative in-situ investigation of dislocation loop motion in Fe9Cr1.5W ferritic/martensitic steel under the coupling effects of constant stress and irradiation	63
Editorial Board	62
Finite element analysis of the stress state and fracture in the TRISO-particle buffer layer	61
Ductility evaluation of nitrided Zircaloy-4 cladding by ring compression testing	58
The incorporation of xenon at point defects and bubbles in uranium mononitride	58
Uranium–plutonium–oxygen phase diagram: Investigating the solvus of fluorite's exsolution	53
Molecular dynamics investigation of dislocation-hydrogen/helium interactions in tungsten	52
Effect of thermal oxidation on helium implanted pure iron	51
Radial hydride fraction with various rod internal pressures and hydrogen contents for Zr-Nb alloy cladding tube	50
Development of an image analysis code for hydrided Zircaloy using Dijkstra's algorithm and sensitivity analysis of radial hydride continuous path	49
Inter-diffusion of nitrogen and helium in IG-110 nuclear graphite	47
Anisotropy study of hydrogen diffusion along different directions of Zr-2.5%Nb alloy pressure tube using neutron imaging	45
Crud deposition behavior on zirconium alloy fuel cladding in high-temperature pressurized water environments	44
Effect of transmutation and active elements on the surface stability of silicon carbide	41
Faulted and Perfect Loop Evolution in Single Crystal Thorium Dioxide under High-Temperature Proton Irradiation	40
Determining the diffusion behavior of point defects in zirconium by a multiscale modelling approach	37
The shear stress required for the splitting of a helical dislocation into a prismatic dislocation loop and a screw dislocation in alpha-iron	37
Raman spectroscopy of uranium nitride kernels	37
Tritium release performance of centrifugally granulated Li2TiO3 pebbles	35
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]	34
Crack self-healing by high-temperature annealing of a 90W7Ni3Fe tungsten heavy alloy	34
Effect of Re aggregation doping configurations on the thermal and mechanical properties of W-Re alloys: A molecular dynamics study	32
Vacancy accumulation mechanism at iron grain boundaries: The influence of grain boundary character and its coupling with grain size	32

Tungsten fiber-reinforced tungsten composites and their thermal stability	31
Investigating the interactions between hydrotalcite and U(IV) nanoparticulates	31
Experimental investigation of Kr diffusion in UO2+: Slight deviations from stoichiometry, significant effects on diffusion kinetics and mechanisms	31
Influence of Cu/W semi-coherent interfacial structure on helium behavior: insights from atomistic simulations	31
Demonstration of an integrated-heating load frame for quantitatively assessing microscale tensile properties of copper and Zircaloy-2	30
A deep learning interatomic potential model for the generation and evolution mechanisms of irradiation defects in yttrium hydride	30