Pressurized water reactor thermal-hydraulic core analysis with the FLICA computer code

1990 ◽  
Vol 124 (3) ◽  
pp. 299-313 ◽  
Author(s):  
P. Raymond ◽  
B. Spindler ◽  
R. Lenain
Keyword(s):  
Computer Code ◽  
Core Analysis ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Water Reactor

Validation of the Pressurized Water Reactor Core Analysis System SEANAP-86 with Measurements in Tests and Operation

1988 ◽  
Vol 100 (3) ◽  
pp. 305-313 ◽  
Author(s):  
C. Ahnert ◽  
J. M. Aragonés ◽  
A. Crespo ◽  
A. Labay ◽  
J. R. León ◽  
...  
Keyword(s):  
Reactor Core ◽  
Core Analysis ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Water Reactor ◽  
Analysis System

scholarly journals Thermodynamic consequences of hydrogen combustion within a containment of pressurized water reactor

2011 ◽  
Vol 32 (4) ◽  
pp. 67-79
Author(s):  
Tomasz Bury
Keyword(s):  
Nuclear Power ◽  
Large Scale ◽  
Nuclear Reactor ◽  
Computer Code ◽  
Hydrogen Combustion ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Water Reactor ◽  
Lumped Parameter ◽  
Loss Of Coolant

Thermodynamic consequences of hydrogen combustion within a containment of pressurized water reactor Gaseous hydrogen may be generated in a nuclear reactor system as an effect of the core overheating. This creates a risk of its uncontrolled combustion which may have a destructive consequences, as it could be observed during the Fukushima nuclear power plant accident. Favorable conditions for hydrogen production occur during heavy loss-of-coolant accidents. The author used an own computer code, called HEPCAL, of the lumped parameter type to realize a set of simulations of a large scale loss-of-coolant accidents scenarios within containment of second generation pressurized water reactor. Some simulations resulted in high pressure peaks, seemed to be irrational. A more detailed analysis and comparison with Three Mile Island and Fukushima accidents consequences allowed for withdrawing interesting conclusions.

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