OOIR: Observatory of International Research

Papers

(The H4-Index of Nuclear Engineering and Design is 26. 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 2022-06-01 to 2026-06-01.)

Article	Citations
Experimental studies on nitrogen’s effect on reactor core cooling during a hot leg SBLOCA in a scaled EPR model	53
Application of deterministic sampling methods to uncertainty quantification in MELCOR severe accident simulation	47
A review on the state of thermal hydraulics research on air ingress scenarios in High-Temperature Gas-cooled Reactors following a D-LOFC	44
Safety margin evaluation of RSG-GAS during LOFA considering ageing-induced degradation of coast-down flow and recent decay heat measurement	44
Dynamic modeling and simulation of the GAMA-AHR	42
Burnup determination of Full-Scale, High-Density U3Si2-Al (4.8 gU/cc) fuel plate using destructive radiochemical technique	41
Building a multiscale framework: An overview of the NEAMS thermal-hydraulics integrated research project	40
Influence of steam deviation, droplets mass flow rate and residual power on dispersed flow film boiling at sub-channel scale in LOCA conditions	38
Rapid deep learning prediction model using satellite imagery for radiation accident Announcement system in Serbia	38
Thermo-fluid dynamic analysis of HLM pool. Circe experiments	37
Preface for special issue “NFT-06“: Nuclear fission technology in Slovenia, Croatia and Serbia	36
State feedback control of HPR1000 average coolant temperature based on dominant pole	34
An educational simulation of a country’s electric power system	34
National context of the recent Spanish research on nuclear fission technology	34
Analysis of NERVA engine performance using point kinetics-based power balance modeling	33
Feasibility of using BeO rods as secondary neutron sources in the long-life fuel cycle high-temperature gas-cooled reactor	32
Experimental study on the rewetting velocity on dry out surface due to stepwise boundary condition changes	32
A viscoplastic approach to corium spreading during a severe nuclear accident	32
Spanish contribution to the development and application of best estimate plus uncertainty methodologies: Past, present and future	31
Static-dynamic coupled analysis of pumping station structure of a nuclear power plant using viscoelastic static-dynamic unified artificial boundary	30
The actual constraints and consequences of the maneuvering operation of PWRs — An optimum seeking approach	29
Assessment of the disposability of radioactive waste inventories for a range of nuclear fuel cycles: Effect of repository size on disposal cost	29
Development and assessment of a reactor system prognosis model with physics-guided machine learning	29
A numerical study on metallic melt infiltration in porous media and the effect of solidification	28
Probability-based assessment of time-varying prestress losses in in-service containment structures	27

Corrigendum to “R&D in advanced technology fuels (ATFs) in Spain” [Nucl. Eng. Des 424, (2024) 113246]	26
Reliability Assessment of Safety-Critical Systems of Nuclear Power Plant using Ordinary Differential Equations and Reachability Graph	26