OOIR: Observatory of International Research

Papers

(The H4-Index of Nuclear Engineering and Design is 23. 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 2021-04-01 to 2025-04-01.)

Article	Citations
Acoustic field study of ultrasonic transducers for nuclear pipelines using an improved Gaussian beam method	60
Importance, influence and limits of CFD radiation modeling for containment atmosphere simulations	53
Experimental study of the transient boiling phenomenon on a vertically placed ribbon	42
Neutronic characteristics of the VVER-1000 fuel assembly with mechanical spectral shift regulation	40
Experimental studies on nitrogen’s effect on reactor core cooling during a hot leg SBLOCA in a scaled EPR model	39
Interaction characteristics of subcooled water jet with high-pressure upward into high-temperature oil in a confined space	38
Effective thermal conductivity prediction of dispersion nuclear fuel elements based on deep learning and property-oriented inverse design	38
An inversion model for burnup history of spent fuels in pebble bed HTGR based on optimization algorithm	38
Optimization of uranium and uranium-thorium fuel utilization in pebble bed for PeLUIt-10 reactor using PEBBED code	33
A comprehensive review of pulsed research reactors: Focus on Russian periodic fast reactors	32
Building a multiscale framework: An overview of the NEAMS thermal-hydraulics integrated research project	31
Fabrication of surrogate oxide spent fuel with various cracking patterns and design of an axial gas transport apparatus	30
Impact of including fuel performance as part of core reload optimization: Application to power uprates	30
Reliability Assessment of Safety-Critical Systems of Nuclear Power Plant using Ordinary Differential Equations and Reachability Graph	28
Editorial Board	28
Editorial Board	27
Validation of RANS simulations on a 61-pin wire-wrapped fast-reactor fuel assembly under the presence of localized blockages	27
Modeling and simulation of the radiolytic deuterium and oxygen generation in heavy water reactors	26
Conceptual design and analysis of a combined passive cooling system for both reactor and spent fuel of the pool-vessel reactor system	26
Editorial Board	25
Study on improvement for the prediction accuracy of natural circulation flow rate by investigating void fraction correlation	24
Analysis and evaluation of the irradiated dimensional and volume change behavior of nuclear graphites	24
Safety analysis and evaluation of transport and storage container for very Low-Level liquid radioactive waste	24
Steam flows in concrete cracks: Thermal behaviour	23
Time averaged tomographic measurements before and after dryout in a simplified BWR subchannel geometry	23

Editorial Board