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Nuclear Engineering and Design : Impact Factor & More

eISSN: 1872-759XpISSN: 0029-5493

Key Metrics

CiteScore
3.5
Impact Factor
< 5
SJR
Q2Mechanical Engineering
SNIP
1.48
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Topics Covered on Nuclear Engineering and Design

Nuclear Engineering and Design Journal Specifications

Indexed in the following public directories

  • Web of Science Web of Science
  • Scopus Scopus
  • Inspec Inspec
  • SJR SJR
Overview
Publisher ELSEVIER SCIENCE SA
Language English
Frequency Monthly
General Details
LanguageEnglish
FrequencyMonthly
Publication Start Year1964
Publisher URLVisit website
Website URLVisit website
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Recently Published Papers in Nuclear Engineering and Design

Immobilization mechanisms of Sr2+ in magnesium potassium phosphate cement: Early hydration, strength development, and leaching resistance
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Dynamic mode decomposition for multi-cycle burnup distribution prediction in the high-temperature gas-cooled reactor
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Leveraging multiple fidelities for thermal-hydraulics uncertainty analyses of fuel assemblies subjected to deformation
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HYDRA-IBRAE/LM calculations and uncertainty analysis of the IAEA benchmark of transition from forced to natural circulation experiment with heavy liquid metal loop
  • 1 Oct 2026
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Neutronic assessment of FeCrAl alloys in a PWR-based small modular reactor
  • 1 Sep 2026
  • Nuclear Engineering and Design
Experimental study of mixing vane angle on 1 × 2 rod bundle under two-phase equilibrium and non-equilibrium flow
  • 1 Aug 2026
  • Nuclear Engineering and Design
Immobilization mechanisms of Sr2+ in magnesium potassium phosphate cement: Early hydration, strength development, and leaching resistance
  • 1 Nov 2026
  • Nuclear Engineering and Design
Dynamic mode decomposition for multi-cycle burnup distribution prediction in the high-temperature gas-cooled reactor
  • 1 Nov 2026
  • Nuclear Engineering and Design
Leveraging multiple fidelities for thermal-hydraulics uncertainty analyses of fuel assemblies subjected to deformation
  • 1 Oct 2026
  • Nuclear Engineering and Design
HYDRA-IBRAE/LM calculations and uncertainty analysis of the IAEA benchmark of transition from forced to natural circulation experiment with heavy liquid metal loop
  • 1 Oct 2026
  • Nuclear Engineering and Design
Neutronic assessment of FeCrAl alloys in a PWR-based small modular reactor
  • 1 Sep 2026
  • Nuclear Engineering and Design
Experimental study of mixing vane angle on 1 × 2 rod bundle under two-phase equilibrium and non-equilibrium flow
  • 1 Aug 2026
  • Nuclear Engineering and Design

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