Journal Report

Nuclear Engineering and Technology

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Journal Information
Journal Title
Nuclear Engineering and Technology
Publisher
Korean Nuclear Society
ISSN
1738-5733
E-ISSN
2234-358X
Database
SCOPUS
Domain
Health Sciences, Physical Sciences, Social Sciences
Classification History
Year A+ A B C
2026 ✓ ✓
2025 ✓ ✓
2024 ✓ ✓
2023 ✓ ✓
2021/2022 ✓ ✓
2020 ✓ ✓
2019 ✓ ✓
2018 ✓
A journal may have more than one classification in the same year. All recorded classifications are displayed.
Recent Articles
Characterisation of annular UO2 pellets fabricated using spark plasma sintering and conventional sintering
Anil Prasad, Andrew Bergeron, Charles Liu et al.
2027-3 Vol. 59 Issue 3 Pages 104775
Early fault warning for redundant sensor groups in nuclear power plants using a Seq2Seq model and quantile-aggregated sequential detection
Yun Chen, Jianxin Chen, Jiawei Hu et al.
2027-3 Vol. 59 Issue 3 Pages 104797
Hybrid genetic algorithm with a GNN-based surrogate model for pipe support design optimization in nuclear power plant
Daeyoung Jeong, Sungryul Kim
2027-3 Vol. 59 Issue 3 Pages 104803
Comprehensive characterization of powder ceramic waste: Implications for TENORM risk assessment and radiation protection
Hanan M. Abdelbary, Mohamed M.E. Breky, Yasser T. Mohamed et al.
2027-3 Vol. 59 Issue 3 Pages 104794
Alkali-activated solidification of spent zeolite adsorbents: Compaction, volume reduction, and waste form performance
Jaehun Lee, Sia Hwang, Jiwon Shin et al.
2027-3 Vol. 59 Issue 3 Pages 104801
Joint fault diagnosis of nuclear main pump sliding bearings under variable operating conditions using multi-task 2D residual network
Cheng Chen, Desheng Zhang, Xiaojing Wang et al.
2027-3 Vol. 59 Issue 3 Pages 104802
Performance assessment of neutron coincidence collars for safeguards measurements of fresh high-assay low-enriched uranium advanced reactor fuels
Donny Hartanto, Jianwei Hu, Robert McElroy
2027-3 Vol. 59 Issue 3 Pages 104809
Gaussian process regression-based prediction of spatial source-term distributions in activated bioshield concrete using limited sampling data
Seok Jun Hong, Nak Woong Yang, Chang Je Park
2027-3 Vol. 59 Issue 3 Pages 104787
Public valuation of a partial transition from large reactors to enhanced-safety small modular reactors: Evidence from South Korea
Moon-Ki Min, Bo-Min Seol, Seung-Hoon Yoo
2027-3 Vol. 59 Issue 3 Pages 104792
Evaluation of the shutdown capability of a soluble boron-free small modular reactor by PRAGMA
Ikje Noh, Hyung Jin Shim
2027-3 Vol. 59 Issue 3 Pages 104799
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Printed: October 31, 2026 08:53