OOIR: Observatory of International Research

Papers

(The H4-Index of Journal of Nuclear Materials is 31. 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 2022-08-01 to 2026-08-01.)

Article	Citations
Impact of anisotropic grain microstructure on the fracture-mechanical properties of ITER grade tungsten plate	133
Editorial Board	86
Editorial Board	72
Finite element analysis of the stress state and fracture in the TRISO-particle buffer layer	67
The incorporation of xenon at point defects and bubbles in uranium mononitride	65
Ductility evaluation of nitrided Zircaloy-4 cladding by ring compression testing	62
Uranium–plutonium–oxygen phase diagram: Investigating the solvus of fluorite's exsolution	56
Radial hydride fraction with various rod internal pressures and hydrogen contents for Zr-Nb alloy cladding tube	55
Inter-diffusion of nitrogen and helium in IG-110 nuclear graphite	54
Raman spectroscopy of uranium nitride kernels	49
Tritium release performance of centrifugally granulated Li2TiO3 pebbles	49
Crack self-healing by high-temperature annealing of a 90W7Ni3Fe tungsten heavy alloy	47
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]	47
Vacancy accumulation mechanism at iron grain boundaries: The influence of grain boundary character and its coupling with grain size	45
Experimental investigation of Kr diffusion in UO2+: Slight deviations from stoichiometry, significant effects on diffusion kinetics and mechanisms	41
Effect of Re aggregation doping configurations on the thermal and mechanical properties of W-Re alloys: A molecular dynamics study	41
Influence of Cu/W semi-coherent interfacial structure on helium behavior: insights from atomistic simulations	41
Investigating the interactions between hydrotalcite and U(IV) nanoparticulates	40
Demonstration of an integrated-heating load frame for quantitatively assessing microscale tensile properties of copper and Zircaloy-2	39
Performance of high-Cr ODS steels under high-temperature neutron irradiation	37
A deep learning interatomic potential model for the generation and evolution mechanisms of irradiation defects in yttrium hydride	37
Post-irradiation examination of AGR-3/4 TRISO fuel compacts using three-dimensional X-ray computed tomography	35
Chromium doping effects on UO2 grain boundary chemistry: A combined experimental and modeling approach	34
Nanopore graphene-tungsten composite with enhanced irradiated helium atoms storage capacity	34
Effect of ion flux on one-dimensional migration of dislocation loops in Fe9Cr1.5W0.4Si F/M steel during in-situ Fe+ irradiation	33

Development of novel multi-element low-activation Fe-based alloys for nuclear and fusion reactor applications	32
Tailoring the radiation induced dislocation loop behavior in the FeCoNiCr alloy via minor alloying strategy	32
Positron annihilation study of the reactor pressure vessel model steels irradiated in the high flux reactor	31
Manufacturing porous U10Zr fuels with controlled porosities by SPS and thermal properties	31
First-principles study on the corrosion characteristics of surface defects for fusion reactor blanket structural steel in liquid lead-lithium environment	31
Corrosion behavior of 316H stainless steel in molten LiF-UF4 and LiF-UF4-ZrF4 salts	31
Effect of Y2O3 addition on the microstructure and liquid LBE cavitation erosion behaviors of Fe-Cr-Al-Ti-C-xY2O3 laser clade coatings	31
Waste acceptance criteria testings of a phosphate-based geopolymer waste form to immobilize radioactive borate waste	31
Effect of point defects on water adsorption on the ThO2{111} surface: A first-principles computational study	31