The In-Vessel Retention (IVR) of molten core debris has been part of the severe accident management strategy for advanced pressurized water reactor (PWR) plant. Generally, the pressure is supposed to successfully be released, and the externally cooled lower head wall mainly experiences the temperature difference which may be more than 1000℃. However, the Fukushima accident shows that a certain pressure (up to 8.0MPa) still exists inside the reactor pressure vessel (RPV). Therefore, in order to make the IVR succeed, it is necessary to investigate the structural integrity of the RPV under the combined internal pressure and the thermal load on the lower head. Therefore, it is supposed that the lower head of RPV is a Hemisphere Shell Structure ...
International audienceIn the event of a severe core meltdown accident in a pressurized water reactor...
In order to enhance the ability of severe accident mitigation for Pressurised Water Reactor (PWR), d...
AbstractExternal reactor vessel cooling (ERVC) for in-vessel retention (IVR) has been considered one...
The strategy denoted as <q>in-vessel retention (IVR)</q> is widely used in severe accident (SA) man...
In existing severe accident codes such as MELCOR and THALES2, rupture of reactor pressure vessel (RP...
Fukushima Daiichi accident emphasized that the complex phenomenology of In Vessel Corium Retention (...
A severe accident management concept, known as ‘in-vessel retention (IVR)’, is widely used in advanc...
The mechanical behaviour of the reactor pressure vessel strongly influences the environmental conseq...
Considering the unlikely core melt down scenario for a light water reactor (LWR) a possible failure ...
International audienceIn order to characterize the timing, mode and size of a possible lower head fa...
A severe accident in a nuclear power plant could result in the relocation of large quantities of mol...
In the study of severe pressurized water reactor accidents, the scenarios that describe the relocati...
The objective of the USNRC supported Lower Head Failure (LHF) Experiment Program at Sandia National ...
A historical review of in-vessel melt retention (IVR) is given, which is a severe accident mitigatio...
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...
In order to enhance the ability of severe accident mitigation for Pressurised Water Reactor (PWR), d...
AbstractExternal reactor vessel cooling (ERVC) for in-vessel retention (IVR) has been considered one...
The strategy denoted as <q>in-vessel retention (IVR)</q> is widely used in severe accident (SA) man...
In existing severe accident codes such as MELCOR and THALES2, rupture of reactor pressure vessel (RP...
Fukushima Daiichi accident emphasized that the complex phenomenology of In Vessel Corium Retention (...
A severe accident management concept, known as ‘in-vessel retention (IVR)’, is widely used in advanc...
The mechanical behaviour of the reactor pressure vessel strongly influences the environmental conseq...
Considering the unlikely core melt down scenario for a light water reactor (LWR) a possible failure ...
International audienceIn order to characterize the timing, mode and size of a possible lower head fa...
A severe accident in a nuclear power plant could result in the relocation of large quantities of mol...
In the study of severe pressurized water reactor accidents, the scenarios that describe the relocati...
The objective of the USNRC supported Lower Head Failure (LHF) Experiment Program at Sandia National ...
A historical review of in-vessel melt retention (IVR) is given, which is a severe accident mitigatio...
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...
In order to enhance the ability of severe accident mitigation for Pressurised Water Reactor (PWR), d...
AbstractExternal reactor vessel cooling (ERVC) for in-vessel retention (IVR) has been considered one...