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Comparisons of Supercritical Loop Flow and Heat Transfer Behavior Under Uniform and Nonuniform High-Flux Heat Inputs
Author: Yang, Dong; Chen, Lin; Feng, Yongchang; Chen, Haisheng
Journal: NUCLEAR SCIENCE AND ENGINEERING. 2023; Vol. 197, Issue 1, pp. 74-91. DOI: 10.1080/00295639.2022.2102391
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A Unified Framework of Stabilized Finite Element Methods for Solving the Boltzmann Transport Equation
Author: He, Qingming; Fang, Chao; Cao, Liangzhi; Zhang, Haoyu
Journal: NUCLEAR SCIENCE AND ENGINEERING. 2023; Vol. 197, Issue 3, pp. 472-484. DOI: 10.1080/00295639.2022.2106733
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A CFD Modeling Coupled with VOF Method and Solidification Model for Molten Jet Breakup at Low Velocity
Author: Liu, Tao; Zhou, Yuan; Zhong, Mingjun; Gong, Houjun
Journal: NUCLEAR SCIENCE AND ENGINEERING. 2023; Vol. 197, Issue 3, pp. 398-412. DOI: 10.1080/00295639.2022.2116379
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Flow-Induced Vibrations of Two Flexible Tubes in Cross Flow
Author: Feng, Zhipeng; Zang, Fenggang; Liu, Shuai; Qi, Huanhuan; Huang, Xuan
Journal: NUCLEAR SCIENCE AND ENGINEERING. 2023; Vol. 197, Issue 3, pp. 428-442. DOI: 10.1080/00295639.2022.2118478
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LQG/LTR Controller Design for Power Control of Small Pressurized Water Reactors Under Four Feedback-Controlled Strategies
Author: Wu, Shifa; Wan, Jiashuang; Chen, Zhi; Liao, Longtao; Xiao, Kai; Wang, Pengfei
Journal: NUCLEAR SCIENCE AND ENGINEERING. 2023; Vol. 197, Issue 4, pp. 660-675. DOI: 10.1080/00295639.2022.2123204
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Investigation of the Inhomogeneous Mechanical and Crack Driving Force of Low Alloy Steel SA508 and Its Welded 309L/308L Stainless Steel Cladding
Author: Wang, Shuai; Xue, He; Wu, Guiyi; Wang, Zheng; Zhao, Kuan; Ni, Chenqiang
Journal: NUCLEAR SCIENCE AND ENGINEERING. 2023; Vol. 197, Issue 4, pp. 623-632. DOI: 10.1080/00295639.2022.2123210
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An Improved Dual Asymmetric Penalized Least Squares Baseline Correction Method for High-Noise Spectral Data Analysis
Author: Shu, Shuangbao; Yu, Ziqiao; Zhang, Jiaxin; Chen, Zhiqiang; Liang, Huajun; Chen, Jingjing
Journal: NUCLEAR SCIENCE AND ENGINEERING. 2023; Vol. 197, Issue 4, pp. 589-600. DOI: 10.1080/00295639.2022.2132101
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High-Fidelity Neutron Transport Solution of High Temperature Gas-Cooled Reactor by Three-Dimensional Linear Source Method of Characteristics
Author: Zhu, Kaijie; Kong, Boran; Zhang, Han; Guo, Jiong; Li, Fu
Journal: NUCLEAR SCIENCE AND ENGINEERING. 2023; Vol. 197, Issue 6, pp. 1174-1196. DOI: 10.1080/00295639.2022.2143706
