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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

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
Numerical study on the influence of internal heat generation on mixed convection heat transfer in a horizontal laminar pipe flow with wall cooling
  • 1 Aug 2026
  • Nuclear Engineering and Design
ROADRUNNER uranium nitride MiniFuel: Experimental design, fabrication and pre-irradiation baseline characterization for accelerated burnup testing
  • 1 Aug 2026
  • Nuclear Engineering and Design
An appropriate crack modeling approach and finite element analysis for stress intensity factors of reactor vessel discontinuities
  • 1 Aug 2026
  • Nuclear Engineering and Design
Analysis of uncertainty and sensitivity in the safety parameters of a VVER-1000 nuclear power plant containment during a loss of coolant accident
  • 1 Aug 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
Numerical study on the influence of internal heat generation on mixed convection heat transfer in a horizontal laminar pipe flow with wall cooling
  • 1 Aug 2026
  • Nuclear Engineering and Design
ROADRUNNER uranium nitride MiniFuel: Experimental design, fabrication and pre-irradiation baseline characterization for accelerated burnup testing
  • 1 Aug 2026
  • Nuclear Engineering and Design
An appropriate crack modeling approach and finite element analysis for stress intensity factors of reactor vessel discontinuities
  • 1 Aug 2026
  • Nuclear Engineering and Design
Analysis of uncertainty and sensitivity in the safety parameters of a VVER-1000 nuclear power plant containment during a loss of coolant accident
  • 1 Aug 2026
  • Nuclear Engineering and Design

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