In a light-water reactor core melt accident, if the reactor pressure vessel (RPV) fails while the reactor coolant system (RCS) at high pressure, the expulsion of molten core debris may pressurize the reactor containment building (RCB) beyond its failure pressure. A failure in the bottom head of the RPV, followed by melt expulsion and blowdown of the RCS, will entrain molten core debris in the high-velocity steam blowdown gas. This chain of events is called a high-pressure melt ejection (HPME). Four mechanisms may cause a rapid increase in pressure and temperature in the reactor containment: (1) blowdown of the RCS, (2) efficient debris-to-gas heat transfer, (3) exothermic metal-steam and metal-oxygen reactions, and (4) hydrogen combustion. ...
Thermohydraulic analysis of postulated accidents will identify system responses to accident scenario...
A general review is given of containment technology for water-coolednuclear reactors, including disc...
Accident conditions involving significant core degradation are termed severe accidents /IAEA: NS-G-2...
Direct Containment Heating (DCH) is a severe reactor accident scenario in which it is postulated tha...
High-pressure melt ejection from PWR vessels has been identified as a severe core accident scenario ...
Two experiments, DCH-3 and DCH-4, were performed at the Surtsey test facility to investigate phenome...
In the course of a postulated severe accident in an NPP, Direct Containment Heating (DCH) may occur ...
The DISCO test facility at Forschungszentrum Karlsruhe (FZK) has been used to perform experiments to...
In the event of a core meltdown accident, one of the accident progression paths is fuel relocation t...
The DISCO-H Test Facility at Forschungszentrum Karlsruhe was set up to perform scaled experiments th...
In some nuclear reactor core melt accidents, a potential exists for molten core debris to be dispers...
In the CONTAINMENT area of SARNET three issues of severe accident phenomenol-ogy are treated which e...
The mechanical behaviour of the reactor pressure vessel strongly influences the environmental conseq...
The accident at the Fukushima Daiichi nuclear power plant has shown us that there may be situations ...
Based on level 2 analyses in IPE (Individual Plant Examination) submittals accident progression, per...
Thermohydraulic analysis of postulated accidents will identify system responses to accident scenario...
A general review is given of containment technology for water-coolednuclear reactors, including disc...
Accident conditions involving significant core degradation are termed severe accidents /IAEA: NS-G-2...
Direct Containment Heating (DCH) is a severe reactor accident scenario in which it is postulated tha...
High-pressure melt ejection from PWR vessels has been identified as a severe core accident scenario ...
Two experiments, DCH-3 and DCH-4, were performed at the Surtsey test facility to investigate phenome...
In the course of a postulated severe accident in an NPP, Direct Containment Heating (DCH) may occur ...
The DISCO test facility at Forschungszentrum Karlsruhe (FZK) has been used to perform experiments to...
In the event of a core meltdown accident, one of the accident progression paths is fuel relocation t...
The DISCO-H Test Facility at Forschungszentrum Karlsruhe was set up to perform scaled experiments th...
In some nuclear reactor core melt accidents, a potential exists for molten core debris to be dispers...
In the CONTAINMENT area of SARNET three issues of severe accident phenomenol-ogy are treated which e...
The mechanical behaviour of the reactor pressure vessel strongly influences the environmental conseq...
The accident at the Fukushima Daiichi nuclear power plant has shown us that there may be situations ...
Based on level 2 analyses in IPE (Individual Plant Examination) submittals accident progression, per...
Thermohydraulic analysis of postulated accidents will identify system responses to accident scenario...
A general review is given of containment technology for water-coolednuclear reactors, including disc...
Accident conditions involving significant core degradation are termed severe accidents /IAEA: NS-G-2...