DSpace Repository

Numerical Simulation of Fluid Flow and Heat Transfer of the Supercritical Water in Different Fuel Rod Channels

Show simple item record

dc.contributor.author Han, Huirui
dc.contributor.author Zhang, Chao
dc.date.accessioned 2018-11-08T20:08:11Z
dc.date.available 2018-11-08T20:08:11Z
dc.date.issued 2018-05
dc.identifier CSME021
dc.identifier.isbn 978-1-77355-023-7
dc.identifier.uri http://hdl.handle.net/10315/35367
dc.identifier.uri http://dx.doi.org/10.25071/10315/35367
dc.description Paper presented at 2018 Canadian Society of Mechanical Engineers International Congress, 27-30 May 2018. en_US
dc.description.abstract The supercritical water-cooled reactor was proposed as one of the Generation IV nuclear systems. Although many research works on the fluid flow and heat transfer of supercritical water in circular channels have been conducted, there is still lack of research on the fluid flow and heat transfer process in fuel bundles used in supercritical water-cooled nuclear reactors. Besides, fuel bundles have multiple fuel rods, the flow is an external flow, not internal flow as that in circle channels, which will cause the difference in the fluid flow phenomenon and heat transfer on the fuel rod cladding surface. In this work, the heat transfer and fluid flow characteristics of the supercritical water in the single-rod channel and the multi-rod channel are simulated numerically. The results show that there are secondary flows in both channels. The circumferential cladding surface temperature variation is large and should be considered in the future fuel rod design. With the same flow rate and heat flux input, the maximum cladding surface temperature in the multi-rod channel is much higher than that in the single-rod channel. Since the maximum cladding surface temperature is an important parameter for the safety of the nuclear reactor operation, it is recommended to use the multi-rod channel model to conduct numerical simulations for the fluid flow and heat transfer of the supercritical water in the Canadian SCWR. en_US
dc.language.iso en en_US
dc.publisher CSME-SCGM en_US
dc.rights The copyright for the paper content remains with the author
dc.subject Heat Transfer en_US
dc.subject SCWR en_US
dc.subject Single-rod en_US
dc.subject Multi-rod en_US
dc.subject Cladding surface temperature en_US
dc.title Numerical Simulation of Fluid Flow and Heat Transfer of the Supercritical Water in Different Fuel Rod Channels en_US
dc.type Article en_US

Files in this item



This item appears in the following Collection(s)

Show simple item record