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Numerical investigation on transverse flow of helical cruciform fuel rod assembly in a lead-bismuth cooled fast reactor

The helical cruciform fuel (HCF) rod assembly is a new type of fuel for the lead-bismuth (LBE) fast reactor. It can be self-positioned and realize a coolant mixing without wrapped wire or grid spacer. This kind of fuel assembly can not only realize the function of the traditional wire-wrapped fuel a...

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Detalhes bibliográficos
Principais autores: Yue Zeng, Huandong Chen, Pingjian Ming
Formato: Artigo
Idioma:Inglês
Publicado em: KeAi Communications Co., Ltd. 2023-03-01
Colecção:International Journal of Advanced Nuclear Reactor Design and Technology
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Acesso em linha:http://www.sciencedirect.com/science/article/pii/S2468605023000285
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