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pro vyhledávání: '"Dutra, Carolina Bourdot"'
Heat pipes can efficiently and passively remove heat in nuclear microreactors. Nevertheless, the flow dynamics within heat pipes present a significant challenge in designing and optimizing them for nuclear energy applications. This work aims to explo
Externí odkaz:
http://arxiv.org/abs/2408.02234
Autor:
Dutra, Carolina Bourdot, Merzari, Elia
Understanding the coolant thermal hydraulics in rod bundles is essential to the design of nuclear reactors. However, flows with low Reynolds numbers present serious modeling challenges, especially in heat transfer and natural convection. They are dif
Externí odkaz:
http://arxiv.org/abs/2308.15561
Autor:
Dutra, Carolina Bourdot, Merzari, Elia
The study of coolant flow behavior in rod bundles is of relevance to the design of nuclear reactors. Although laminar and turbulent flows have been researched extensively, there are still gaps in understanding the process of laminar-turbulent transit
Externí odkaz:
http://arxiv.org/abs/2308.15548
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