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Experimental investigation of the spatial evolution of local flow parameters in vertical LBE–N2 bubbly flow

To support closure-model development for thermal-hydraulic analysis of SGTR/HXTR-related two-phase flow in lead-cooled fast reactors, a separate-effect experimental study was conducted on lead–bismuth eutectic (LBE)–nitrogen bubbly flow in a vertical circular pipe using a loop-type high-temperature...

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Detalhes bibliográficos
Principais autores: Zihao Zhu, Bin Li, Bin Hou, Lina Zhu, Kefan Geng, Bo Pang, Yangbin Deng, Xi Huang
Formato: Artigo
Idioma:Inglês
Publicado em: KeAi Communications Co., Ltd. 2026-06-01
Colecção:International Journal of Advanced Nuclear Reactor Design and Technology
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Acesso em linha:http://www.sciencedirect.com/science/article/pii/S2468605026000311
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