Nuclear Engineering and Design

Papers
(The H4-Index of Nuclear Engineering and Design is 24. 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 2021-08-01 to 2025-08-01.)
ArticleCitations
Experimental studies on nitrogen’s effect on reactor core cooling during a hot leg SBLOCA in a scaled EPR model50
Development of plutonium fuel facility decommissioning technology to accelerate glovebox dismantling and reduce air-fed suits based operations44
Corrigendum to “R&D in advanced technology fuels (ATFs) in Spain” [Nucl. Eng. Des 424, (2024) 113246]41
Performance evaluation of AHWR flux mapping system during normal operational scenarios40
Performance evaluation of nuclear fuel in a reactor based on the CAREM 2540
Assessment of TRU burning in a molten salt reactor moderated by zirconium hydride rods39
State feedback control of HPR1000 average coolant temperature based on dominant pole37
A review on the state of thermal hydraulics research on air ingress scenarios in High-Temperature Gas-cooled Reactors following a D-LOFC35
Rapid deep learning prediction model using satellite imagery for radiation accident Announcement system in Serbia34
Reliability Assessment of Safety-Critical Systems of Nuclear Power Plant using Ordinary Differential Equations and Reachability Graph33
Thermo-fluid dynamic analysis of HLM pool. Circe experiments31
Building a multiscale framework: An overview of the NEAMS thermal-hydraulics integrated research project29
Experimental analysis of the start-up of a natural circulation loop in single and two-phase flow29
Study on improvement for the prediction accuracy of natural circulation flow rate by investigating void fraction correlation29
Editorial Board29
“Ion sputtering – thermal separation” technology for spent nuclear fuel processing28
Effect of interfacial area concentration on one-dimensional code simulation of adiabatic two-phase flows in vertical large size channels27
Modeling of Am-241 as an alternative fuel source in a radioisotope thermoelectric generator27
In-plane fluidelastic instability study of a tube bundle with a rotated triangular layout and small pitch ratio26
Loading method of Li rods for tritium production using High-Temperature Gas-Cooled reactor for fusion reactors26
An educational simulation of a country’s electric power system26
National context of the recent Spanish research on nuclear fission technology25
Evaluation of thermal–hydraulic characteristics of reactor coolant system and helically coiled steam generator based on performance tests with SMART-ITL24
Depressurization of nuclear power plants through a silica gel-based system24
A viscoplastic approach to corium spreading during a severe nuclear accident24
Preface for special issue “NFT-06“: Nuclear fission technology in Slovenia, Croatia and Serbia24
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