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1 Zeszyty Naukowe Politechniki Świętokrzyskiej. Mechanika

1 1999

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Some thermal-hydraulic aspects of reflooding of an overheated, partly degraded nuclear reactor core

Frid W., Miettinen J., Sjöberg A.

Zeszyty Naukowe Politechniki Świętokrzyskiej. Mechanika

1999

Z. 67

235--244

In studies of postulated, unmitigated severe accidents in LWRs it is assumed that cooling of the reactor core is lost which leads to core uncovery and heat-up. core degradation and eventually melt-down of the core. Restoring water supply to the reactor core in order to prevent core damage and to terminate accident progression is the main objective of the accident management. In some Boiling Water Reactors it is necessary to consider a possibility that the reactor may become critical during the reflooding phase. The reason is that the melting of the control rods and their relocation from the core is likely to start before the melting and relocation of the fuel. The two-phase flow and heat transfer phenomena associated with reflooding and quenching of the reactor core are complex and not completely understood, especially under severe accident conditions due to high fuel temperatures and. In the case of recriticality, strong thermal-hydraulic transients when the core reaches critical conditions. In this paper, the two-phase flow and heat transfer phenomena during reflooding of an overheated, partly degraded core are discussed. The reflooding model developed for the RECRIT code is briefly described, as well as some validation against experimental data.