Nuclear Engineering and Design

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 2021-11-01 to 2025-11-01.)
ArticleCitations
Probability-based assessment of time-varying prestress losses in in-service containment structures60
Study on heat transfer enhancement mechanism and performance evaluation of streamline spirally coiled tubes49
Building a multiscale framework: An overview of the NEAMS thermal-hydraulics integrated research project45
Disruptive thermal-spectrum molten salt breeder reactor fuel cycle technologies44
Corrigendum to “R&D in advanced technology fuels (ATFs) in Spain” [Nucl. Eng. Des 424, (2024) 113246]43
Experimental studies on nitrogen’s effect on reactor core cooling during a hot leg SBLOCA in a scaled EPR model39
State feedback control of HPR1000 average coolant temperature based on dominant pole36
A review on the state of thermal hydraulics research on air ingress scenarios in High-Temperature Gas-cooled Reactors following a D-LOFC35
Scaling methodologies and similarity analysis for thermal hydraulics test facility development for water-cooled small modular reactor33
Assessment of TRU burning in a molten salt reactor moderated by zirconium hydride rods32
Preface for special issue “NFT-06“: Nuclear fission technology in Slovenia, Croatia and Serbia31
National context of the recent Spanish research on nuclear fission technology31
Development of plutonium fuel facility decommissioning technology to accelerate glovebox dismantling and reduce air-fed suits based operations30
An educational simulation of a country’s electric power system30
Influence of steam deviation, droplets mass flow rate and residual power on dispersed flow film boiling at sub-channel scale in LOCA conditions29
Selection of projects’ primary and secondary mitigation actions through optimization methods in nuclear decommissioning projects27
Development and assessment of a reactor system prognosis model with physics-guided machine learning27
Rapid deep learning prediction model using satellite imagery for radiation accident Announcement system in Serbia27
Transient behavior of a molten salt fast reactor under two-phase flow conditions with helium bubbling26
MELCOR 2.2 iPWR LOCA type accident analysis, PART I: Thermal-hydraulics25
The fluid-structure interaction effect on seismic response of double CAP1400 spent fuel storage racks25
Mass transfer between a continuous oxide phase (U-O-Zr) and a steel droplet at liquid state: Potential impact on corium pool behaviour during in-vessel melt retention25
Implications of using nanoparticles on the performance and safety of nuclear systems25
Reactor core design of UPR-s: A nuclear reactor for silence thermoelectric system NUSTER25
Performance evaluation of nuclear fuel in a reactor based on the CAREM 2525
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