Fusion Engineering and Design

Aims & Scope

The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy.

Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.

View Aims & Scope

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Metrics & Ranking

Impact Factor

Year	Value
2025	2

SJR (SCImago Journal Rank)

Year	Value
2024	0.727

Quartile

Year	Value
2024	Q1

h-index

Year	Value
2024	95

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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, Engineering and Materials Science, 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.

• ARC: A compact, high-field, fusion nuclear science facility and demonstration power plant with demountable magnets

  Citation: 472

  Authors: B.N., J., T.R., F.J., J.M., P., C., D.A., H.S., C.B., J., C., D.G.

• Present development status of EUROFER and ODS-EUROFER for application in blanket concepts

  Citation: 451

  Authors: R., A., M., M., E., A., A.-A. F., C., A.-M., P., N., R., E., G., J.W., B.v.d., E., W.

• Operating temperature windows for fusion reactor structural materials

  Citation: 432

  Authors: S.J, N.M

• CAD-based interface programs for fusion neutron transport simulation

  Citation: 395

  Authors: Y.

• Blanket/first wall challenges and required R&D on the pathway to DEMO

  Citation: 302

  Authors: Mohamed, Neil B., Sergey, Alice, Siegfried, Arthur, Mike

• Research status and issues of tungsten plasma facing materials for ITER and beyond

  Citation: 297

  Authors: Y., J.W., G., R.P., J., V., E.

• On the exploration of innovative concepts for fusion chamber technology

  Citation: 294

  Authors: M.A, The APEX, A, N, K, S, M, S, S, T, P, B, R, K, M.Z, N, D, C, M, H, R, R, R, S, J, A, D, M, M, T

• Overview of EU DEMO design and R&D activities

  Citation: 288

  Authors: G., R., D., C., T., S., C., M., J., B., C., F., R.

• DEMO design activity in Europe: Progress and updates

  Citation: 261

  Authors: G., C., L., W., L., R., C., S., F., M., V., C., E., U., T., C., A., R., A., F., B., G., N., M.Q., C., R., J.H.

• A new approach to evaluate irradiation hardening of ion-irradiated ferritic alloys by nano-indentation techniques

  Citation: 255

  Authors: Ryuta, Yoshiyuki, Kiyohiro, Akihiko

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