-
Screening of structural materials for the LEGO space reactor based on neutronic-thermal-mechanical coupled analysi
Author: Zhang, Biao; Wu, Jiawen; Qiao, Jianshu; Huang, Dongli; Zhou, Tao; Xu, Chuanlong
Journal: ANNALS OF NUCLEAR ENERGY. 2026; Vol. 234, Issue , pp. -. DOI: 10.1016/j.anucene.2026.112307
-
A novel fuel form: Ceramic-encased fusible-matrix dispersion microencapsulated fuel for enhanced uranium loading in special-purpose gas-cooled microreactor
Author: Zheng, Junqiang; Zhang, Ruixiao; He, Ya'nan; Wu, Yingwei; Zhang, Jing; Su, G. H
Journal: ANNALS OF NUCLEAR ENERGY. 2026; Vol. 234, Issue , pp. -. DOI: 10.1016/j.anucene.2026.112300
-
A numerical study of bubble departure characteristics and the dominant mechanism under periodic external vibratio
Author: Zhu, Chunxiao; Feng, Yi; Gao, Tianyi; Mo, Zhengyu; Du, Min; Zheng, Jiaxin; Xu, Xin; Zhang, Qinyi; Sun, Licheng
Journal: ANNALS OF NUCLEAR ENERGY. 2026; Vol. 234, Issue , pp. -. DOI: 10.1016/j.anucene.2026.112312
-
Performance study of a continuous SCWO reactor for radioactive TBP based on CF
Author: Shi, Erbing; Zhang, Zhongjie; Wang, Peiran; Zhang, Zijun; Ren, Xin; Liu, Yuan; Han, Jiaqi
Journal: ANNALS OF NUCLEAR ENERGY. 2026; Vol. 234, Issue , pp. -. DOI: 10.1016/j.anucene.2026.112311
-
Experimental study of condensation induced water hammer caused by the accumulation of condensate water in the steam pipelin
Author: Liang, Minchao; Zhao, Jiaming; Zhang, Jiarui; Xue, Rongyang; Yang, Yili; Guo, Wentao; Wang, Shengfei
Journal: ANNALS OF NUCLEAR ENERGY. 2026; Vol. 234, Issue , pp. -. DOI: 10.1016/j.anucene.2026.112310
-
A multi-scale framework with machine learning for hydrogen transport properties in nuclear thermal propulsio
Author: Li, Keyi; Zhang, Haochun; Zhou, Ziyang; You, Ersheng
Journal: ANNALS OF NUCLEAR ENERGY. 2026; Vol. 234, Issue , pp. -. DOI: 10.1016/j.anucene.2026.112321
-
Research on fault diagnosis method of rotating components in NPPs based on multi-domain feature fusion strateg
Author: Xia, Yubo; Xu, Yifan; Zhang, Zhigang; Xia, Genglei
Journal: ANNALS OF NUCLEAR ENERGY. 2026; Vol. 234, Issue , pp. -. DOI: 10.1016/j.anucene.2026.112328
-
Experimental study on contact melting of in-reactor bundle assembly components by corium crust based on simulant material
Author: Ma, Junjie; Chen, Wenzhen; Hao, Jianli
Journal: ANNALS OF NUCLEAR ENERGY. 2026; Vol. 234, Issue , pp. -. DOI: 10.1016/j.anucene.2026.112331
