Annals of Nuclear Energy

Aims & Scope

Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology.

Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics.

Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering.

Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal.

Also, papers that deal with policy or economics are not within the scope of the journal.

View Aims & Scope

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Metrics & Ranking

Impact Factor

Year	Value
2025	2.3
2024	1.90

SJR (SCImago Journal Rank)

Year	Value
2024	0.897

Quartile

Year	Value
2024	Q1

Journal Rank

Year	Value
2024	5715

Journal Citation Indicator

Year	Value
2024	5110

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Abstracting & Indexing

Journal is indexed in leading academic databases, ensuring global visibility and accessibility of our peer-reviewed research.

• Scopus
• Google Scholar
• Web of Science

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Subjects & Keywords

Journal’s research areas, covering key disciplines and specialized sub-topics in Energy, designed to support cutting-edge academic discovery.

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Most Cited Articles

The Most Cited Articles section features the journal's most impactful research, based on citation counts. These articles have been referenced frequently by other researchers, indicating their significant contribution to their respective fields.

• The Serpent Monte Carlo code: Status, development and applications in 2013

  Citation: 1171

  Authors: Jaakko, Maria, Tuomas, Ville, Toni

• Calculation of radiation attenuation coefficients for shielding concretes

  Citation: 951

  Authors: I.I.

• OpenMC: A state-of-the-art Monte Carlo code for research and development

  Citation: 801

  Authors: Paul K., Nicholas E., Bryan R., Adam G., Benoit, Kord

• Overview of the FLUKA code

  Citation: 761

  Authors: Giuseppe, Till, Francesco, Pik Wai, Luigi Salvatore, Alberto, Alfredo, Anton, Anton, Andrea, Alessio, Pablo Garcia, Johannes, Stefan, Paola R., Vasilis, George

• The OpenMC Monte Carlo particle transport code

  Citation: 363

  Authors: Paul K., Benoit

• CAD-based Monte Carlo program for integrated simulation of nuclear system SuperMC

  Citation: 334

  Authors: Yican, Jing, Huaqing, Guangyao, Lijuan, Pengcheng, Liqin

• TRIPOLI-4®, CEA, EDF and AREVA reference Monte Carlo code

  Citation: 307

  Authors: E., F., C.M., E., F.X., C., Y.K., F., A., O., J.C., T., A.

• RMC – A Monte Carlo code for reactor core analysis

  Citation: 297

  Authors: Kan, Zeguang, Ding, Jin’gang, Qi, Yishu, Jiankai, Jialong, Xiao, Ganglin

• Photon attenuation coefficients of concrete includes barite in different rate

  Citation: 283

  Authors: I., H., B., S., C.

• Development of a multi-dimensional thermal-hydraulic system code, MARS 1.3.1

  Citation: 230

  Authors: J.-J., K.S., B.D., W.J.

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