Jinyi Cao , Jianchuang Sun , Xiangfei Meng , Wenchao Zhang , Jincheng Wang , Qian Li , Benan Cai , Weihua Cai
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引用次数: 0
Abstract
Helical petal-shaped fuel rods have the characteristics of increased heat transfer area and self-supporting positioning, which makes them have great potential for application in small modular reactors. By employing the multi-scale coupled numerical model, the flow and heat transfer characteristics of the petal-shaped bundle in hexagonal arrangement were obtained under natural circulation conditions. The results indicated that the spatial structure of flow channel exhibited a centrally symmetric distribution. Consistent flow and heat transfer behaviors were obtained at symmetric positions. Additionally, fluid viscosity exerted the most significant influence on flow resistance coefficient. Meanwhile, vortices that develop in the opposite direction resulted in flow losses, which induced variations in the resistance coefficient along the channel. Finally, the applicability of existing flow and heat transfer correlations was evaluated under natural circulation conditions. This study has provided significant theoretical guidance for engineering application of the petal-shaped fuel rods.
期刊介绍:
Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field.
Please note the following:
1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy.
2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc.
3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.