Numerical study on the thermo-hydraulic behaviors of the Directionally-Alternated wire-wrapped fuel assembly in lead-cooled fast reactors based on SSTSAS k-ω-k-ε four-equation model

Annals of Nuclear Energy 2026

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Authors: Yunxiang Li, Runsheng Yang, Yuefeng Guo, Xingkang Su, Xingkang Su, Yuping Zhou, Jian Hong, Yuxing Liu, Zinan Huang, Xin Su, Xin Su, Y. Y. Zhang
+2 more WenJun Hu, Long Gu
DOI: 10.1016/j.anucene.2026.112119
Cited by: 1
References: 29

Fields of Study & Subjects

Heat transfer and supercritical fluids Nuclear reactor physics and engineering Heat and Mass Transfer in Porous Media

Publication details

Journal / source
Annals of Nuclear Energy
Publisher
Elsevier BV
Volume
230
Pages
112119–112119
Publication date
19 January 2026
Language
EN