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 2021-06-01 to 2025-06-01.)

Article	Citations
Editorial Board	179
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]	77
Effect of thermal oxidation on helium implanted pure iron	62
Determining the diffusion behavior of point defects in zirconium by a multiscale modelling approach	59
Predictions of the full-life pressurised water stress corrosion cracking behaviour of 690 weld joints	58
He nanobubble driven W surface growth during low-energy He ion irradiations	57
Quantitative in-situ investigation of dislocation loop motion in Fe9Cr1.5W ferritic/martensitic steel under the coupling effects of constant stress and irradiation	56
Calculation of grain boundary diffusion coefficients in γU-Mo using atomistic simulations	55
Dose-dependent strain localization and embrittlement in ferritic materials: A predictive approach based on sub-grain plasticity modelling	52
Atomistic modelling of iodine-oxygen interactions in strained sub-oxides of zirconium	51
The vacancy-mediated diffusion of transition metal solutes in tungsten: Atomic Kinetic Monte Carlo simulations	50
In-situ ion irradiation study of alloy 709 stainless steels with different processing histories	49
Crack self-healing by high-temperature annealing of a 90W7Ni3Fe tungsten heavy alloy	45
Experimental investigation of Kr diffusion in UO2+: Slight deviations from stoichiometry, significant effects on diffusion kinetics and mechanisms	45
Effect of scratch depth on high cycle fatigue behavior of Alloy 690TT stream generator tube	43
Dislocation loop coarsening and shape evolution upon annealing neutron-irradiated RAFM steel	42
Uranium–plutonium–oxygen phase diagram: Investigating the solvus of fluorite's exsolution	40
Nanopore graphene-tungsten composite with enhanced irradiated helium atoms storage capacity	39
Effect of ion flux on one-dimensional migration of dislocation loops in Fe9Cr1.5W0.4Si F/M steel during in-situ Fe+ irradiation	38
Insight into the interfacial microstructure and chemistry of hot isostatically pressed AA6061-AA6061 bonds for U-10Mo fuel cladding application	37
A comprehensive atomistic investigation on the cascade induced helium bubble motion in bcc iron for neutron irradiated RAFM steels	36
Effect of transmutation and active elements on the surface stability of silicon carbide	36
Unpacking model inadequacy: The quantification of silver release from TRISO fuel by considering empirical and mechanistic approaches	35
Development of novel multi-element low-activation Fe-based alloys for nuclear and fusion reactor applications	34
The incorporation of xenon at point defects and bubbles in uranium mononitride	33

A molecular dynamics study of a cascade induced irradiation creep mechanism in pure copper	33
Monitoring the gradual change in oxidation state during surface oxidation or reduction of uranium oxides by photoemission spectroscopy of the 5f states	33
Corrosion behavior of a series of combinatorial physical vapor deposition coatings on SiC in a simulated boiling water reactor environment	33
Development of an image analysis code for hydrided Zircaloy using Dijkstra's algorithm and sensitivity analysis of radial hydride continuous path	31
Radial hydride fraction with various rod internal pressures and hydrogen contents for Zr-Nb alloy cladding tube	31
Development of GD-containing austenitic stainless steel	30
Effect of Re aggregation doping configurations on the thermal and mechanical properties of W-Re alloys: A molecular dynamics study	30