OpenAlex is a bibliographic catalogue of scientific papers, authors and institutions accessible in open access mode, named after the Library of Alexandria. It's citation coverage is excellent and I hope you will find utility in this listing of citing articles!
If you click the article title, you'll navigate to the article, as listed in CrossRef. If you click the Open Access links, you'll navigate to the "best Open Access location". Clicking the citation count will open this listing for that article. Lastly at the bottom of the page, you'll find basic pagination options.
Requested Article:
Thermal fatigue analysis of structures subjected to liquid metal jets at different temperatures in the Gen-IV nuclear energy system
Yingjie Wang, Mingjun Wang, Kang Jia, et al.
Energy (2022) Vol. 256, pp. 124681-124681
Closed Access | Times Cited: 14
Yingjie Wang, Mingjun Wang, Kang Jia, et al.
Energy (2022) Vol. 256, pp. 124681-124681
Closed Access | Times Cited: 14
Showing 14 citing articles:
Analysis of flow-induced vibration of wire-wrapped fuel assemblies under the liquid metal axial flow in the Gen-IV nuclear reactor
Hongjian Guo, Wei Li, Jing Zhang, et al.
Annals of Nuclear Energy (2023) Vol. 188, pp. 109811-109811
Closed Access | Times Cited: 15
Hongjian Guo, Wei Li, Jing Zhang, et al.
Annals of Nuclear Energy (2023) Vol. 188, pp. 109811-109811
Closed Access | Times Cited: 15
Energy transfer and interaction between liquid metal with water
Lin Zhang, Chang Deng, Xiaojing Liu
Energy (2023) Vol. 288, pp. 129865-129865
Closed Access | Times Cited: 11
Lin Zhang, Chang Deng, Xiaojing Liu
Energy (2023) Vol. 288, pp. 129865-129865
Closed Access | Times Cited: 11
Experimental Research on Fluid Elastic Instability in Rod Bundles Subjected to Lead-bismuth Eutectic (LBE) Cross-Flow
Yibo Yin, Gao Pu-zhen, Xinyang Yu, et al.
Nuclear Engineering and Technology (2025), pp. 103514-103514
Open Access
Yibo Yin, Gao Pu-zhen, Xinyang Yu, et al.
Nuclear Engineering and Technology (2025), pp. 103514-103514
Open Access
Numerical investigation of natural convection heat transfer of water/ SWCNT nanofluid flow in a triangular cavity with cold fluid injection
Reza Sarlak, Azher M. Abed, Omid Ali Akbari, et al.
Progress in Nuclear Energy (2022) Vol. 155, pp. 104513-104513
Closed Access | Times Cited: 16
Reza Sarlak, Azher M. Abed, Omid Ali Akbari, et al.
Progress in Nuclear Energy (2022) Vol. 155, pp. 104513-104513
Closed Access | Times Cited: 16
Galerkin scheme on entropy generation in complex fluid involving gyrotactic microorganisms on cylinder/surface via solar thermal radiations
Kanit Mukdasai, Umar Nazir
Case Studies in Thermal Engineering (2023) Vol. 45, pp. 102995-102995
Open Access | Times Cited: 7
Kanit Mukdasai, Umar Nazir
Case Studies in Thermal Engineering (2023) Vol. 45, pp. 102995-102995
Open Access | Times Cited: 7
Experimental and numerical analysis of the liquid metal mixing phenomenon in complex jets of Gen-IV nuclear system
Yingjie Wang, Zhixian Lai, Hanrui Qiu, et al.
International Journal of Heat and Mass Transfer (2023) Vol. 213, pp. 124330-124330
Closed Access | Times Cited: 6
Yingjie Wang, Zhixian Lai, Hanrui Qiu, et al.
International Journal of Heat and Mass Transfer (2023) Vol. 213, pp. 124330-124330
Closed Access | Times Cited: 6
Investigation of the thermal-hydraulic characteristics of SCO2 in a modified hybrid airfoil channel
Zhen Li, Daogang Lu, M. Lin, et al.
Energy (2024) Vol. 308, pp. 132838-132838
Closed Access | Times Cited: 1
Zhen Li, Daogang Lu, M. Lin, et al.
Energy (2024) Vol. 308, pp. 132838-132838
Closed Access | Times Cited: 1
Design on cladding of central measuring shroud against thermal shock in FR based on elastoplastic model
Shu Zheng, Daogang Lu, Qiong Cao, et al.
Annals of Nuclear Energy (2023) Vol. 195, pp. 110141-110141
Closed Access | Times Cited: 3
Shu Zheng, Daogang Lu, Qiong Cao, et al.
Annals of Nuclear Energy (2023) Vol. 195, pp. 110141-110141
Closed Access | Times Cited: 3
Analysis of unprotected loss of flow accident in a sodium cooled fast reactor using coupled thermal hydraulics neutronics code ASTRA
Yadu Narendran, K. Natesan, K. Devan, et al.
Progress in Nuclear Energy (2023) Vol. 163, pp. 104801-104801
Closed Access | Times Cited: 2
Yadu Narendran, K. Natesan, K. Devan, et al.
Progress in Nuclear Energy (2023) Vol. 163, pp. 104801-104801
Closed Access | Times Cited: 2
Study on the most severe condition for structural assessment of nuclear fuel transport package under impact loading
Yuchen Hao, Jinhua Wang, Bin Wu, et al.
Progress in Nuclear Energy (2022) Vol. 153, pp. 104447-104447
Closed Access | Times Cited: 3
Yuchen Hao, Jinhua Wang, Bin Wu, et al.
Progress in Nuclear Energy (2022) Vol. 153, pp. 104447-104447
Closed Access | Times Cited: 3
Research on fine analysis and accelerated prediction technology for thermal stratification in the upper plenum of the “Monju” reactor
Jinchao Li, Hao Qian, Guangliang Chen, et al.
Case Studies in Thermal Engineering (2024) Vol. 60, pp. 104844-104844
Open Access
Jinchao Li, Hao Qian, Guangliang Chen, et al.
Case Studies in Thermal Engineering (2024) Vol. 60, pp. 104844-104844
Open Access
Design on Cladding of Central Measuring Shroud Against Thermal Shock in Fr Based on Elastoplastic Model
Shu Zheng, Daogang Lu, Qiong Cao, et al.
(2023)
Closed Access
Shu Zheng, Daogang Lu, Qiong Cao, et al.
(2023)
Closed Access
Analysis of fluid structure interaction between fuel elements and the coolant in Xi’an Pulsed Reactor core under seismic conditions
Pan Hu, Zhenhui Ma, Tengyue Ma, et al.
Frontiers in Energy Research (2023) Vol. 11
Open Access
Pan Hu, Zhenhui Ma, Tengyue Ma, et al.
Frontiers in Energy Research (2023) Vol. 11
Open Access
Experimental study on boiling two-phase of liquid sodium along a 7-rod bundle – Part Ⅱ: Heat transfer characteristics
Yandong Hou, Liu Wang, Kui Zhang, et al.
Annals of Nuclear Energy (2022) Vol. 183, pp. 109677-109677
Closed Access
Yandong Hou, Liu Wang, Kui Zhang, et al.
Annals of Nuclear Energy (2022) Vol. 183, pp. 109677-109677
Closed Access
