The preliminary results of PHOENICS and RELAP5 show that the current numerical models are adequate in predicting steam flow and stratification patterns in the upper Drywell of a BWR containment subsequent to a blow-down event. However, additional modeling is required in order to study detailed local phenomena such as condensation with non-condensables, natural convection, and stratification effects. Analytically, the intermittence modified similarity solutions show great promise. Once {gamma} is accounted for, the jet's turbulent shear stress can be determined with excellent accuracy
Condensing nozzle flows have been used extensively to validate wet steam models. Many test cases are...
This analysis calculates the velocity profile and recirculation ratio in the aspirator region of an ...
International audienceCorrosion product deposits in the secondary side of nuclear plant steam genera...
The primary objective of this thesis is to characterize the behavior of steam jets within an enclose...
This paper compares the three-dimensional numerical simulation with the experimental data of a steam...
This paper deals with the analysis of the blow-down phenomenon which is of interest in the safety of...
Historically, thermal hydraulics analyses on Large Break Loss of Coolant Accidents (LOCA) have been ...
The fouling of heat transfer surfaces in kraft recovery boilers is a significant concern for the pul...
Scholars usually ignore the non-equilibrium condensing effects in turbulence-model comparative studi...
The Pressure Suppression Pool (PSP) of a Boiling Water Reactor (BWR) is a large heat sink designed t...
Engineers desire to be able to predict natural convection flow and heat transfer in high Rayleigh n...
The validation of a CFD code for light-water reactor containment applications requires among others ...
This paper presents an evaluation of the applicability of a numerical analysis model to the transien...
Thermal hydraulics in nuclear engineering including multifluid, multiphase flow phenomena is indispe...
Natural convection is the dominant flow regime inside containments following the short-term blowdown...
Condensing nozzle flows have been used extensively to validate wet steam models. Many test cases are...
This analysis calculates the velocity profile and recirculation ratio in the aspirator region of an ...
International audienceCorrosion product deposits in the secondary side of nuclear plant steam genera...
The primary objective of this thesis is to characterize the behavior of steam jets within an enclose...
This paper compares the three-dimensional numerical simulation with the experimental data of a steam...
This paper deals with the analysis of the blow-down phenomenon which is of interest in the safety of...
Historically, thermal hydraulics analyses on Large Break Loss of Coolant Accidents (LOCA) have been ...
The fouling of heat transfer surfaces in kraft recovery boilers is a significant concern for the pul...
Scholars usually ignore the non-equilibrium condensing effects in turbulence-model comparative studi...
The Pressure Suppression Pool (PSP) of a Boiling Water Reactor (BWR) is a large heat sink designed t...
Engineers desire to be able to predict natural convection flow and heat transfer in high Rayleigh n...
The validation of a CFD code for light-water reactor containment applications requires among others ...
This paper presents an evaluation of the applicability of a numerical analysis model to the transien...
Thermal hydraulics in nuclear engineering including multifluid, multiphase flow phenomena is indispe...
Natural convection is the dominant flow regime inside containments following the short-term blowdown...
Condensing nozzle flows have been used extensively to validate wet steam models. Many test cases are...
This analysis calculates the velocity profile and recirculation ratio in the aspirator region of an ...
International audienceCorrosion product deposits in the secondary side of nuclear plant steam genera...