Nuclear Engineering and Design

Papers
(The H4-Index of Nuclear Engineering and Design is 23. 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 2021-09-01 to 2025-09-01.)
ArticleCitations
Experimental studies on nitrogen’s effect on reactor core cooling during a hot leg SBLOCA in a scaled EPR model54
Performance evaluation of nuclear fuel in a reactor based on the CAREM 2544
Corrigendum to “R&D in advanced technology fuels (ATFs) in Spain” [Nucl. Eng. Des 424, (2024) 113246]44
Performance evaluation of AHWR flux mapping system during normal operational scenarios42
Assessment of TRU burning in a molten salt reactor moderated by zirconium hydride rods42
State feedback control of HPR1000 average coolant temperature based on dominant pole39
A review on the state of thermal hydraulics research on air ingress scenarios in High-Temperature Gas-cooled Reactors following a D-LOFC38
Reliability Assessment of Safety-Critical Systems of Nuclear Power Plant using Ordinary Differential Equations and Reachability Graph34
Rapid deep learning prediction model using satellite imagery for radiation accident Announcement system in Serbia34
Thermo-fluid dynamic analysis of HLM pool. Circe experiments31
Experimental analysis of the start-up of a natural circulation loop in single and two-phase flow30
“Ion sputtering – thermal separation” technology for spent nuclear fuel processing29
Building a multiscale framework: An overview of the NEAMS thermal-hydraulics integrated research project29
Modeling of Am-241 as an alternative fuel source in a radioisotope thermoelectric generator29
Effect of interfacial area concentration on one-dimensional code simulation of adiabatic two-phase flows in vertical large size channels28
In-plane fluidelastic instability study of a tube bundle with a rotated triangular layout and small pitch ratio27
Loading method of Li rods for tritium production using High-Temperature Gas-Cooled reactor for fusion reactors27
National context of the recent Spanish research on nuclear fission technology26
An educational simulation of a country’s electric power system26
Preface for special issue “NFT-06“: Nuclear fission technology in Slovenia, Croatia and Serbia25
Depressurization of nuclear power plants through a silica gel-based system25
Evaluation of thermal–hydraulic characteristics of reactor coolant system and helically coiled steam generator based on performance tests with SMART-ITL24
A viscoplastic approach to corium spreading during a severe nuclear accident24
Implications of using nanoparticles on the performance and safety of nuclear systems23
Quantification of uncertainties due to manufacturing tolerances using deterministic sampling methods23
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