A Study of Subcooled Film-Boiling Heat Transfer under Reactivity-Initiated Accident Conditions in Light Water Reactors

1984 ◽  
Vol 88 (3) ◽  
pp. 331-341 ◽  
Author(s):  
Nobuaki Ohnishi ◽  
Kiyomi Ishijima ◽  
Sadamitsu Tanzawa
Keyword(s):  
Heat Transfer ◽  
Boiling Heat Transfer ◽  
Film Boiling ◽  
Light Water Reactors ◽  
Light Water ◽  
Water Reactors ◽  
Accident Conditions

Iodine-steel reactions under severe accident conditions in light-water reactors

1996 ◽  
Vol 166 (3) ◽  
pp. 357-365 ◽  
Author(s):  
F. Funke ◽  
G.-U. Greger ◽  
S. Hellmann ◽  
A. Bleier ◽  
W. Morell
Keyword(s):  
Severe Accident ◽  
Light Water Reactors ◽  
Light Water ◽  
Water Reactors ◽  
Accident Conditions

Performance of Containment Sprays for Light Water Reactors and Evaluation of the Heat Transfer

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

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

2006 ◽  
Author(s):  
Henryk Anglart
Keyword(s):  
Heat Transfer ◽  
Heat Transfer Enhancement ◽  
Phenomenological Model ◽  
Nuclear Reactors ◽  
Light Water Reactors ◽  
Transfer Enhancement ◽  
Light Water ◽  
Operational Conditions ◽  
Transfer Processes ◽  
Water Reactors

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.

Simulation of the Natural Convection Test of Phenix Reactor Using Modified ATHLET

2012 ◽  
Author(s):  
Chong Zhou ◽  
Klaus Huber ◽  
Xu Cheng
Keyword(s):  
Heat Transfer ◽  
Experimental Data ◽  
Natural Convection ◽  
Fast Reactor ◽  
Atomic Energy Commission ◽  
Computer Code ◽  
Light Water Reactors ◽  
Light Water ◽  
Water Reactors ◽  
Alternative Energies

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.

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