The characterization of molten corium–concrete interaction (MCCI) has increasingly become a cause of concern because, in the case of a severe nuclear accident, the core could meltdown and release radiation into the environment. The objective of this study was to determine the thermochemical impact of metal content in the corium and analyze the effect of corium metal content on ablation depth, corium temperature, its viscosity and surface heat flux, and production of hydrogen, carbon monoxide, and carbon dioxide. The governing heat transfer equations were solved while considering the various thermochemical reactions in the existing numerical code in a comprehensive way. The developed MCCI model in CORQUENCH was validated against the data ava...
International audienceIn case of in-vessel corium retention during a severe accident in a light wate...
International audienceDuring severe accidents in nuclear reactors, the core is partly melted. With t...
International audienceDuring a severe accident in a PWR reactor, the oxide nuclear fuel (UO2 or MOX)...
International audienceDuring a severe accident in a nuclear reactor, extreme temperatures may be rea...
The early stages of a severe accident are characterised by a loss of cooling capability in the react...
International audienceDuring a severe accident in a nuclear reactor, extreme temperatures may be rea...
International audienceDuring a severe accident in a Pressurized or Boiling Water nuclear reactor, ex...
International audienceDuring a severe accident in a nuclear reactor, extreme temperatures may be rea...
International audienceMolten corium is considered to form in a severe accident at the Fukushima Daii...
International audienceDuring a severe accident in a pressurized water reactor, very high temperature...
International audienceSevere accident with core meltdown is a threat to the containment integrity. A...
Integral large-scale vessel retention experiments have been performed using up to 60 kg of prototypi...
International audienceIn case of in-vessel corium retention during a severe accident in a light wate...
International audienceDuring severe accidents in nuclear reactors, the core is partly melted. With t...
International audienceDuring a severe accident in a PWR reactor, the oxide nuclear fuel (UO2 or MOX)...
International audienceDuring a severe accident in a nuclear reactor, extreme temperatures may be rea...
The early stages of a severe accident are characterised by a loss of cooling capability in the react...
International audienceDuring a severe accident in a nuclear reactor, extreme temperatures may be rea...
International audienceDuring a severe accident in a Pressurized or Boiling Water nuclear reactor, ex...
International audienceDuring a severe accident in a nuclear reactor, extreme temperatures may be rea...
International audienceMolten corium is considered to form in a severe accident at the Fukushima Daii...
International audienceDuring a severe accident in a pressurized water reactor, very high temperature...
International audienceSevere accident with core meltdown is a threat to the containment integrity. A...
Integral large-scale vessel retention experiments have been performed using up to 60 kg of prototypi...
International audienceIn case of in-vessel corium retention during a severe accident in a light wate...
International audienceDuring severe accidents in nuclear reactors, the core is partly melted. With t...
International audienceDuring a severe accident in a PWR reactor, the oxide nuclear fuel (UO2 or MOX)...