Following the pioneering work and the model by Yamanouchi in Japan in 1968, small progress has been made in relation to the predictive capabilities of reflood models. Reflood is an important period (time window) of the Large Break Loss of Coolant Accident (LBLOCA) in Pressurized and Boiling Water Reactors (BWR and PWR): two dimensional effect occur in conduction heat transfer from the nuclear fuel to the fluid; key parameters of the phenomenon occur in a space of about 0.01 m along the flow direction in te core of PWR and BWR. The present document fixes the point of view and the status of knowledge of the phenomenon at UNIPI (it is at the absi of further developments of the research activity).
Present capabilities of advanced thermal-hydraulic codes in the prediction of reflood phenomena
Ambrosini WalterPrimo
Methodology
;D'Auria F.
Ultimo
Supervision
1992-01-01
Abstract
Following the pioneering work and the model by Yamanouchi in Japan in 1968, small progress has been made in relation to the predictive capabilities of reflood models. Reflood is an important period (time window) of the Large Break Loss of Coolant Accident (LBLOCA) in Pressurized and Boiling Water Reactors (BWR and PWR): two dimensional effect occur in conduction heat transfer from the nuclear fuel to the fluid; key parameters of the phenomenon occur in a space of about 0.01 m along the flow direction in te core of PWR and BWR. The present document fixes the point of view and the status of knowledge of the phenomenon at UNIPI (it is at the absi of further developments of the research activity).I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.
