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 2021-05-01 to 2025-05-01.)
ArticleCitations
Implications of HALEU fuel on the design of SMRs and micro-reactors60
Burnup determination of Full-Scale, High-Density U3Si2-Al (4.8 gU/cc) fuel plate using destructive radiochemical technique55
Assessment of the burnup characteristics of UO2 and MOX fuel in the mixed solid and annular rod configuration44
Experimental studies on nitrogen’s effect on reactor core cooling during a hot leg SBLOCA in a scaled EPR model41
Development of plutonium fuel facility decommissioning technology to accelerate glovebox dismantling and reduce air-fed suits based operations39
Corrigendum to “R&D in advanced technology fuels (ATFs) in Spain” [Nucl. Eng. Des 424, (2024) 113246]38
A numerical study on metallic melt infiltration in porous media and the effect of solidification38
Comparative study of a glovebox dismantling facility for manual and remote glovebox dismantlement activities38
Performance evaluation of nuclear fuel in a reactor based on the CAREM 2534
Study on a leakage rate predictive model with Application in Multi-Conditions conversion for Double-Offset butterfly valves32
Development and assessment of a reactor system prognosis model with physics-guided machine learning31
Performance evaluation of AHWR flux mapping system during normal operational scenarios31
Measurement of corium surface tension using the maximum bubble pressure29
Application of deterministic sampling methods to uncertainty quantification in MELCOR severe accident simulation28
Thermo-fluid dynamic analysis of HLM pool. Circe experiments27
Reliability Assessment of Safety-Critical Systems of Nuclear Power Plant using Ordinary Differential Equations and Reachability Graph27
Assessment of TRU burning in a molten salt reactor moderated by zirconium hydride rods27
Validation of RANS simulations on a 61-pin wire-wrapped fast-reactor fuel assembly under the presence of localized blockages26
Editorial Board25
Study on improvement for the prediction accuracy of natural circulation flow rate by investigating void fraction correlation24
The fluid-structure interaction effect on seismic response of double CAP1400 spent fuel storage racks23
Building a multiscale framework: An overview of the NEAMS thermal-hydraulics integrated research project23
“Ion sputtering – thermal separation” technology for spent nuclear fuel processing23
Effect of inclination angle of lower tube on saturated pool boiling heat transfer of upper tube23
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