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Progress in Nuclear Energy : Impact Factor & More

eISSN: 1878-4224pISSN: 0149-1970

Key Metrics

CiteScore
3.8
Impact Factor
< 5
SJR
Q2Waste Management and Disposal
SNIP
1.38
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Progress in Nuclear Energy Journal Specifications

Indexed in the following public directories

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  • Inspec Inspec
Overview
Publisher PERGAMON-ELSEVIER SCIENCE LTD
Language English
Frequency Bi-monthly
General Details
LanguageEnglish
FrequencyBi-monthly
Publication Start Year1956
Publisher URLVisit website
Website URLVisit website
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Recently Published Papers in Progress in Nuclear Energy

Node assigned physics-informed neural networks for thermal–hydraulic system simulation: CVH/FL/HS modules
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Effect of Ni2+ and Cr3+ on electrodeposition of uranium dioxide in LiCl–KCl molten salt
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Numerical analysis of heat transfer enhancement using nanoaerosol gas in an elbowed shell-and-tube heat exchanger under high-temperature gas-cooled nuclear reactor conditions
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Minimum-dose path planning in radioactive environments based on the Deep Q-Network
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Numerical simulation on thermal-hydraulic characteristics of new passive residual heat removal system with spherical check valve for pool-type SFR
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Subchannel-scale CFD simulation of thermal-hydraulics in a PWR full core with mixing vane spacer grids
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Node assigned physics-informed neural networks for thermal–hydraulic system simulation: CVH/FL/HS modules
  • 1 Jul 2026
  • Progress in Nuclear Energy
Effect of Ni2+ and Cr3+ on electrodeposition of uranium dioxide in LiCl–KCl molten salt
  • 1 Jul 2026
  • Progress in Nuclear Energy
Numerical analysis of heat transfer enhancement using nanoaerosol gas in an elbowed shell-and-tube heat exchanger under high-temperature gas-cooled nuclear reactor conditions
  • 1 Jul 2026
  • Progress in Nuclear Energy
Minimum-dose path planning in radioactive environments based on the Deep Q-Network
  • 1 Jul 2026
  • Progress in Nuclear Energy
Numerical simulation on thermal-hydraulic characteristics of new passive residual heat removal system with spherical check valve for pool-type SFR
  • 1 Jul 2026
  • Progress in Nuclear Energy
Subchannel-scale CFD simulation of thermal-hydraulics in a PWR full core with mixing vane spacer grids
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