This paper presents an analysis of the failure of lower vessel head during a core meltdown accident. The analysis is limited to PWR systems with no penetration tubes attached to the lower vessel head. The case considered is characterized by a small quantity of corium and a relatively slow discharge into the lower plenum. The assumption of the breakup of the jet stream results in the solidification of debris particles and the formation of a debris bed thermally attacking the lower head wall. Detailed analyses were performed to determine the debris/water interaction, ablation of the lower head wall, and the time of vessel failure. Parameters which have significant effect on the results were identified. Parametric studies were performed to ref...
Debris generated during the blowdown phase of a Loss of Coolant Accident (LOCA) is a big concern in ...
International audienceIn the event of a severe core meltdown accident in a pressurised water reactor...
The efficacy of external flooding of a reactor vessel as a severe accident management strategy is as...
International audienceIn order to characterize the timing, mode and size of a possible lower head fa...
In the study of severe pressurized water reactor accidents, the scenarios that describe the relocati...
An analysis has been carried out to assess the potential of a melting attack upon the reactor vessel...
Consulta en la Biblioteca ETSI Industriales (Riunet)[ES] In the present Master Thesis a hypothetical...
The USNRC/SNL OLHF program was carried out within the framework of an OECD project. This program con...
International audienceIn the event of a severe core meltdown accident in a pressurized water reactor...
The mechanical behaviour of the reactor pressure vessel strongly influences the environmental conseq...
A postulated severe loss of coolant accident in a nuclear reactor can lead to significant core damag...
International audienceIn PWR severe accident scenarios, involving a relocation of corium (core melt)...
Fukushima Daiichi accident emphasized that the complex phenomenology of In Vessel Corium Retention (...
In existing severe accident codes such as MELCOR and THALES2, rupture of reactor pressure vessel (RP...
The efficacy of external flooding of a reactor vessel as a severe accident management strategy is as...
Debris generated during the blowdown phase of a Loss of Coolant Accident (LOCA) is a big concern in ...
International audienceIn the event of a severe core meltdown accident in a pressurised water reactor...
The efficacy of external flooding of a reactor vessel as a severe accident management strategy is as...
International audienceIn order to characterize the timing, mode and size of a possible lower head fa...
In the study of severe pressurized water reactor accidents, the scenarios that describe the relocati...
An analysis has been carried out to assess the potential of a melting attack upon the reactor vessel...
Consulta en la Biblioteca ETSI Industriales (Riunet)[ES] In the present Master Thesis a hypothetical...
The USNRC/SNL OLHF program was carried out within the framework of an OECD project. This program con...
International audienceIn the event of a severe core meltdown accident in a pressurized water reactor...
The mechanical behaviour of the reactor pressure vessel strongly influences the environmental conseq...
A postulated severe loss of coolant accident in a nuclear reactor can lead to significant core damag...
International audienceIn PWR severe accident scenarios, involving a relocation of corium (core melt)...
Fukushima Daiichi accident emphasized that the complex phenomenology of In Vessel Corium Retention (...
In existing severe accident codes such as MELCOR and THALES2, rupture of reactor pressure vessel (RP...
The efficacy of external flooding of a reactor vessel as a severe accident management strategy is as...
Debris generated during the blowdown phase of a Loss of Coolant Accident (LOCA) is a big concern in ...
International audienceIn the event of a severe core meltdown accident in a pressurised water reactor...
The efficacy of external flooding of a reactor vessel as a severe accident management strategy is as...