OOIR: Observatory of International Research

Papers

(The H4-Index of Nuclear Engineering and Design is 25. 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 2022-01-01 to 2026-01-01.)

Article	Citations
Corrigendum to “R&D in advanced technology fuels (ATFs) in Spain” [Nucl. Eng. Des 424, (2024) 113246]	65
Assessment of wall heat flux partitioning model for two-phase CFD	44
Experimental studies on nitrogen’s effect on reactor core cooling during a hot leg SBLOCA in a scaled EPR model	44
Thermo-fluid dynamic analysis of HLM pool. Circe experiments	38
Validation of RANS simulations on a 61-pin wire-wrapped fast-reactor fuel assembly under the presence of localized blockages	35
Assessment of TRU burning in a molten salt reactor moderated by zirconium hydride rods	34
Preface for special issue “NFT-06“: Nuclear fission technology in Slovenia, Croatia and Serbia	33
Development of plutonium fuel facility decommissioning technology to accelerate glovebox dismantling and reduce air-fed suits based operations	32
National context of the recent Spanish research on nuclear fission technology	32
An educational simulation of a country’s electric power system	32
Performance evaluation of nuclear fuel in a reactor based on the CAREM 25	31
Using ex-core detectors and deep neural networks for monitoring power distribution in small space reactors	28
Development and validation of theoretical-computational model for nuclear powered hydrogen production: A case study for Saudi Arabia	28
“Ion sputtering – thermal separation” technology for spent nuclear fuel processing	28
Implications of using nanoparticles on the performance and safety of nuclear systems	28
Effect of inclination angle of lower tube on saturated pool boiling heat transfer of upper tube	27
Simulation and optimization of a conical type swirl-vane separator in nuclear SG	27
Application of deterministic sampling methods to uncertainty quantification in MELCOR severe accident simulation	27
Loading method of Li rods for tritium production using High-Temperature Gas-Cooled reactor for fusion reactors	27
Performance evaluation of AHWR flux mapping system during normal operational scenarios	27
In-plane fluidelastic instability study of a tube bundle with a rotated triangular layout and small pitch ratio	27
Comparative study of a glovebox dismantling facility for manual and remote glovebox dismantlement activities	27
Safety margin evaluation of RSG-GAS during LOFA considering ageing-induced degradation of coast-down flow and recent decay heat measurement	26
Effect of rolling motions on the single and two-phase pressure drop in annulus channel with helical-finned heater for floating nuclear reactor	26
A review on the state of thermal hydraulics research on air ingress scenarios in High-Temperature Gas-cooled Reactors following a D-LOFC	25

OECD/NEA PKL-4 benchmark activity. Code assessment of the relevant phenomena associated to a blind IBLOCA experiment	25
Dynamic modeling and simulation of the GAMA-AHR	25