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
Rapid deep learning prediction model using satellite imagery for radiation accident Announcement system in Serbia	38
Influence of steam deviation, droplets mass flow rate and residual power on dispersed flow film boiling at sub-channel scale in LOCA conditions	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
An educational simulation of a country’s electric power system	34
National context of the recent Spanish research on nuclear fission technology	34
State feedback control of HPR1000 average coolant temperature based on dominant pole	34
Analysis of NERVA engine performance using point kinetics-based power balance modeling	33
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
Feasibility of using BeO rods as secondary neutron sources in the long-life fuel cycle high-temperature gas-cooled reactor	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
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
The actual constraints and consequences of the maneuvering operation of PWRs — An optimum seeking approach	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

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