Modeling of Spacer Influence on Post-Dryout Heat Transfer in Heated Channels

Author(s):  
Henryk Anglart

Post-dryout heat transfer plays an important role in safe and economical operations of Light Water Reactors (LWR). This type of heat transfer is avoided under normal operational conditions of nuclear reactors; however, it may occur in transient or accidential situations. To estimate the risk of clad damages due to increase of temperature associated with the occurrence of post-dryout, it is necessary to properly model heat transfer processes under such conditions. The influence of various parameters on heat transfer downstream of spacer has been investigated. It is concluded that heat transfer enhancement due to spacers is largely under-predicted for flows with relatively low quality. For such flows the effect of droplets impinging heated walls is significant and must properly be taken into account. The phenomenological model presented in this paper shows a superior accuracy over correlations and presents a potential to capture the phenomenon of rewetting that occurs downstream of spacers.

1981 ◽  
Vol 54 (1) ◽  
pp. 54-67 ◽  
Author(s):  
Mitsugu Tanaka ◽  
Hironori Watanabe ◽  
Kazuichiro Hashimoto ◽  
Yasuo Motoki ◽  
Mitsuo Naritomi ◽  
...  

Author(s):  
Chong Zhou ◽  
Klaus Huber ◽  
Xu Cheng

The sodium-cooled fast reactor (SFR) is gathering worldwide attention for its features of the fast-spectrum reactor and closed fuel recycle system. This paper presents the modification of the ATHLET code for application to SFRs. The thermal-hydraulic computer code ATHLET is developed by Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) in Germany for light water reactors analysis. In this paper, a sodium properties package is implemented in to the ATHLET code, and heat transfer correlations for sodium are also added for heat transfer prediction. To evaluate the capability of the modified code, the Phenix reactor, a SFR operated by French Alternative Energies and Atomic Energy Commission (CEA) from 1973 to 2009, is modeled. The scenario of transient from forced to natural convection is simulated and analyzed. The results are compared with the experimental data of the natural convection ultimate test of the Phenix facility. Results achieved so far indicate good applicability of the modified ATHLET code.


2018 ◽  
Vol 20 (7) ◽  
pp. 4708-4720 ◽  
Author(s):  
Ericmoore Jossou ◽  
Ubong Eduok ◽  
Nelson Y. Dzade ◽  
Barbara Szpunar ◽  
Jerzy A. Szpunar

Uranium-containing metallic systems such as U3Si2 are potential Accident Tolerant Fuels (ATFs) for Light Water Reactors (LWRs) and the next generation of nuclear reactors.


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