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Numerical study on the effects of guide thimble on critical heat flux in a 5 × 5 fuel assembly.

Authors :
Cong, Tenglong
Gong, Jiaqi
Xiao, Yao
Gu, Hanyang
Source :
Annals of Nuclear Energy. Sep2022, Vol. 175, pN.PAG-N.PAG. 1p.
Publication Year :
2022

Abstract

• The deviations between CHFs predicted by current model and the lookup table are less than 20%. • The introduce of the guide thimble can upgrade the CHF for the assembly by 3.45%. • The guide thimble can alter the transverse location of boiling crisis. • The inter-channel lateral mixing intensity between the innermost channels and the adjacent channels was suppressed by the guide thimble. Rod bundle with guide thimble is a typical structure in the PWR fuel assembly. The thermohydraulics in the channel adjacent to the guide thimble are affected by the non-heated tube, introducing different characteristics in critical heat flux (CHF). In the current work, the CHF of 5 × 5 rod bundle with guide thimble at the center was predicted using the Eulerian two-fluid framework coupled with the critical heat flux model for heat transfer deterioration at the heated wall. The local thermal-hydraulic parameters as well as CHF values were compared with these without guide thimble. It was found that the CHF in the fuel assembly with thimble was slightly larger than that in the assembly without thimble. The lateral locations of boiling crisis were altered by the existence of the guide thimble. The inter-channel cross flow was also suppressed by the guide thimble due to its effect on the flow and thermal boundaries of the subchannels. The results obtained in this work can be used to support the safety analysis in the fuel assembly with guide thimble. [ABSTRACT FROM AUTHOR]

Details

Language :
English
ISSN :
03064549
Volume :
175
Database :
Academic Search Index
Journal :
Annals of Nuclear Energy
Publication Type :
Academic Journal
Accession number :
157523913
Full Text :
https://doi.org/10.1016/j.anucene.2022.109206