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 2021-11-01 to 2025-11-01.)

Article	Citations
Impact of anisotropic grain microstructure on the fracture-mechanical properties of ITER grade tungsten plate	224
Faulted and Perfect Loop Evolution in Single Crystal Thorium Dioxide under High-Temperature Proton Irradiation	105
Editorial Board	74
Quantitative in-situ investigation of dislocation loop motion in Fe9Cr1.5W ferritic/martensitic steel under the coupling effects of constant stress and irradiation	70
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]	67
Effect of thermal oxidation on helium implanted pure iron	64
Development of novel multi-element low-activation Fe-based alloys for nuclear and fusion reactor applications	62
Nanopore graphene-tungsten composite with enhanced irradiated helium atoms storage capacity	60
Insight into the interfacial microstructure and chemistry of hot isostatically pressed AA6061-AA6061 bonds for U-10Mo fuel cladding application	55
Evolution of IFMIF-DONES' heart: System overview of the Test Cell	50
Monitoring the gradual change in oxidation state during surface oxidation or reduction of uranium oxides by photoemission spectroscopy of the 5f states	50
Chromium doping effects on UO2 grain boundary chemistry: A combined experimental and modeling approach	46
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	45
Cluster dynamics modeling of Mn-Ni-Si precipitates coupled with radiation-induced segregation in low-Cu reactor pressure vessel steels	43
Atomistic modelling of iodine-oxygen interactions in strained sub-oxides of zirconium	41
Crud deposition behavior on zirconium alloy fuel cladding in high-temperature pressurized water environments	40
Investigating zirconium alloy corrosion with advanced experimental techniques: A review	39
Positron annihilation study of the reactor pressure vessel model steels irradiated in the high flux reactor	39
Wire and arc additive manufacturing fabrication of ODS-RAFM steels and preliminary evaluation on microstructures and mechanical properties	38
Investigation on the failure mechanistic evolution of fretting corrosion of Alloy 690 with increasing cycles in high-temperature water	38
Uranium–plutonium–oxygen phase diagram: Investigating the solvus of fluorite's exsolution	38
Progress in additive manufacturing of pure tungsten for plasma-facing component applications	37
Unpacking model inadequacy: The quantification of silver release from TRISO fuel by considering empirical and mechanistic approaches	36
Demonstration of an integrated-heating load frame for quantitatively assessing microscale tensile properties of copper and Zircaloy-2	36
The vacancy-mediated diffusion of transition metal solutes in tungsten: Atomic Kinetic Monte Carlo simulations	36

Experimental investigation of Kr diffusion in UO2+: Slight deviations from stoichiometry, significant effects on diffusion kinetics and mechanisms	34
The incorporation of xenon at point defects and bubbles in uranium mononitride	34
Understanding the local thermal conductivity evolution of neutron irradiated U3Si2 dispersion fuel via state-of-the-art thermo-reflectance measurements	34
Dislocation loop coarsening and shape evolution upon annealing neutron-irradiated RAFM steel	33
Effect of Re aggregation doping configurations on the thermal and mechanical properties of W-Re alloys: A molecular dynamics study	33
Dose-dependent strain localization and embrittlement in ferritic materials: A predictive approach based on sub-grain plasticity modelling	32
Effect of point defects on water adsorption on the ThO2{111} surface: A first-principles computational study	32
Waste acceptance criteria testings of a phosphate-based geopolymer waste form to immobilize radioactive borate waste	32
Editorial Board	32