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 2021-08-01 to 2025-08-01.)

Article	Citations
Editorial Board	198
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]	89
Effect of thermal oxidation on helium implanted pure iron	70
Determining the diffusion behavior of point defects in zirconium by a multiscale modelling approach	65
He nanobubble driven W surface growth during low-energy He ion irradiations	64
Dose-dependent strain localization and embrittlement in ferritic materials: A predictive approach based on sub-grain plasticity modelling	57
Calculation of grain boundary diffusion coefficients in γU-Mo using atomistic simulations	57
Atomistic modelling of iodine-oxygen interactions in strained sub-oxides of zirconium	56
In-situ ion irradiation study of alloy 709 stainless steels with different processing histories	54
Manufacturing porous U10Zr fuels with controlled porosities by SPS and thermal properties	53
Experimental investigation of Kr diffusion in UO2+: Slight deviations from stoichiometry, significant effects on diffusion kinetics and mechanisms	53
Predictions of the full-life pressurised water stress corrosion cracking behaviour of 690 weld joints	47
Incipient corrosion of FeCrAl alloys in H3BO3- and LiOH-containing pure water at 360 °C and 18.5 MPa	46
Crack self-healing by high-temperature annealing of a 90W7Ni3Fe tungsten heavy alloy	43
Uranium–plutonium–oxygen phase diagram: Investigating the solvus of fluorite's exsolution	40
Effect of point defects on water adsorption on the ThO2{111} surface: A first-principles computational study	39
Monitoring the gradual change in oxidation state during surface oxidation or reduction of uranium oxides by photoemission spectroscopy of the 5f states	39
Effect of scratch depth on high cycle fatigue behavior of Alloy 690TT stream generator tube	37
Burst characteristics of advanced accident-tolerant FeCrAl cladding under temperature transient testing	37
Investigating the interactions between hydrotalcite and U(IV) nanoparticulates	36
Molecular dynamics investigation of dislocation-hydrogen/helium interactions in tungsten	36
Quantitative in-situ investigation of dislocation loop motion in Fe9Cr1.5W ferritic/martensitic steel under the coupling effects of constant stress and irradiation	35
Radial hydride fraction with various rod internal pressures and hydrogen contents for Zr-Nb alloy cladding tube	34
Development of an image analysis code for hydrided Zircaloy using Dijkstra's algorithm and sensitivity analysis of radial hydride continuous path	34
Helium causing disappearance of a/2<111> dislocation loops in binary Fe-Cr ferritic alloys	32

Development of GD-containing austenitic stainless steel	32
Effect of transmutation and active elements on the surface stability of silicon carbide	32
Neutron irradiation tolerance of potassium-doped and rhenium-alloyed tungsten	31
Effect of ion flux on one-dimensional migration of dislocation loops in Fe9Cr1.5W0.4Si F/M steel during in-situ Fe+ irradiation	31
Vacancy accumulation mechanism at iron grain boundaries: The influence of grain boundary character and its coupling with grain size	31
Raman spectroscopy of uranium nitride kernels	30
A comprehensive atomistic investigation on the cascade induced helium bubble motion in bcc iron for neutron irradiated RAFM steels	30
Corrosion behavior of a series of combinatorial physical vapor deposition coatings on SiC in a simulated boiling water reactor environment	30
Nanopore graphene-tungsten composite with enhanced irradiated helium atoms storage capacity	30
The incorporation of xenon at point defects and bubbles in uranium mononitride	30