OOIR: Observatory of International Research

Papers

(The H4-Index of Nuclear Engineering and Design is 27. 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 2022-05-01 to 2026-05-01.)

Article	Citations
Experimental studies on nitrogen’s effect on reactor core cooling during a hot leg SBLOCA in a scaled EPR model	73
Thermo-fluid dynamic analysis of HLM pool. Circe experiments	48
Preface for special issue “NFT-06“: Nuclear fission technology in Slovenia, Croatia and Serbia	47
National context of the recent Spanish research on nuclear fission technology	44
An educational simulation of a country’s electric power system	42
Analysis of heat pipe cooled reactor startup characteristics by multi-physics coupling simulation based on MOOSE framework	41
SAM-ML: Integrating data-driven closure with nuclear system code SAM for improved modeling capability	39
Robust a posteriori estimation of probit-lognormal seismic fragility curves via sequential design of experiments and constrained reference prior	38
Assessment of the disposability of radioactive waste inventories for a range of nuclear fuel cycles: Effect of repository size on disposal cost	37
Derivation and validation of a turbulent Prandtl number model for LBE in rod bundle channels	37
Simulation and optimization of a conical type swirl-vane separator in nuclear SG	36
Bubble generation and migration behavior in SGTR accident of LFR from a series of experiments	36
Application of deterministic sampling methods to uncertainty quantification in MELCOR severe accident simulation	35
Loading method of Li rods for tritium production using High-Temperature Gas-Cooled reactor for fusion reactors	33
Effect of rolling motions on the single and two-phase pressure drop in annulus channel with helical-finned heater for floating nuclear reactor	33
A review on the state of thermal hydraulics research on air ingress scenarios in High-Temperature Gas-cooled Reactors following a D-LOFC	32
Safety margin evaluation of RSG-GAS during LOFA considering ageing-induced degradation of coast-down flow and recent decay heat measurement	32
Burnup determination of Full-Scale, High-Density U3Si2-Al (4.8 gU/cc) fuel plate using destructive radiochemical technique	31
Dynamic modeling and simulation of the GAMA-AHR	31
Building a multiscale framework: An overview of the NEAMS thermal-hydraulics integrated research project	30
Rapid deep learning prediction model using satellite imagery for radiation accident Announcement system in Serbia	29
Challenges in high-fidelity thermal–hydraulic simulation of SFR cores: Insights and PACA-S4FR solutions	29
Transient behavior of a molten salt fast reactor under two-phase flow conditions with helium bubbling	28
Real-time point-kinetics: Empirical laws, frontiers, and energy consistency	28
Corrigendum to “R&D in advanced technology fuels (ATFs) in Spain” [Nucl. Eng. Des 424, (2024) 113246]	28

A viscoplastic approach to corium spreading during a severe nuclear accident	27
Feasibility of using BeO rods as secondary neutron sources in the long-life fuel cycle high-temperature gas-cooled reactor	27
Experimental study on the rewetting velocity on dry out surface due to stepwise boundary condition changes	27