Thermal hydraulic analysis of a PWR loaded with annular fuel rods

Thermal hydraulic analysis of a PWR loaded with annular fuel rods

In 2006, the final report of the MIT Center for Advanced Nuclear Energy Center the project entitled High Performance Fuel Design for Next Generation PWR’s presented the proposal of an internal and external cooled ring fuel with the objective of increasing the power density of a PWR reactor without c...

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Bibliographic Details
Main Authors: Wallen Ferreira De Souza, Maria Auxiliadora Fortini Veloso, Antonella Lombardi Costa, Clubia Pereira
Format: Article
Language:English
Published: Brazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR) 2021-07-01
Series:Brazilian Journal of Radiation Sciences
Subjects:
annular fuel
subchannel code
sthirp
thermal model
Online Access:https://bjrs.org.br/revista/index.php/REVISTA/article/view/1336
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