Presented is an analysis of the results of the CSTI-1, CSTI-3, and CWTI-11 reactor material experiments in which a jet of molten corium initially at 3080/sup 0/K was directed downward upon a stainless steel plate. The experiments are a continuation of a program of reactor material tests investigating LWR severe accident phenomena. Objective of the present analysis is to determine the existence or nonexistence of a corium crust during impingement from comparison of the measured heatup of the plate (as measured by thermocouples imbedded immediately beneath the steel surface) with model calculations assuming alternately the presence and absence of a stable crust during impingement
Reactor safety experiments for studying the reactions of a molten core (corium) with water and/or co...
The DISCO-H experiments simulate melt ejection scenarios under low system pressure in severe acciden...
In-vessel melt retention is a vital safety design that is incorporated in some nuclear reactors to p...
Integral large-scale vessel retention experiments have been performed using up to 60 kg of prototypi...
The strategy used in ASTRID Sodium Fast Reactor Demonstrator to mitigate the consequences of a postu...
International audienceDuring Severe Accidents (SAs) in Light Water Reactors (LWRs), the core heat up...
International audienceAbstract This paper deals with ablation of a solid by a high temperature liqui...
International audienceIn the framework of the European IVMR project, dedicated to the assessment of ...
International audienceSevere accident with core meltdown is a threat to the containment integrity. A...
International audienceDuring a severe accident in a nuclear reactor, extreme temperatures may be rea...
It is important to understand the mechanisms of quenching molten corium material when estimating the...
AbstractExternal reactor vessel cooling (ERVC) for in-vessel retention (IVR) has been considered one...
The early stages of a severe accident are characterised by a loss of cooling capability in the react...
The characterization of molten corium–concrete interaction (MCCI) has increasingly become a cause of...
Fukushima Daiichi accident emphasized that the complex phenomenology of In Vessel Corium Retention (...
Reactor safety experiments for studying the reactions of a molten core (corium) with water and/or co...
The DISCO-H experiments simulate melt ejection scenarios under low system pressure in severe acciden...
In-vessel melt retention is a vital safety design that is incorporated in some nuclear reactors to p...
Integral large-scale vessel retention experiments have been performed using up to 60 kg of prototypi...
The strategy used in ASTRID Sodium Fast Reactor Demonstrator to mitigate the consequences of a postu...
International audienceDuring Severe Accidents (SAs) in Light Water Reactors (LWRs), the core heat up...
International audienceAbstract This paper deals with ablation of a solid by a high temperature liqui...
International audienceIn the framework of the European IVMR project, dedicated to the assessment of ...
International audienceSevere accident with core meltdown is a threat to the containment integrity. A...
International audienceDuring a severe accident in a nuclear reactor, extreme temperatures may be rea...
It is important to understand the mechanisms of quenching molten corium material when estimating the...
AbstractExternal reactor vessel cooling (ERVC) for in-vessel retention (IVR) has been considered one...
The early stages of a severe accident are characterised by a loss of cooling capability in the react...
The characterization of molten corium–concrete interaction (MCCI) has increasingly become a cause of...
Fukushima Daiichi accident emphasized that the complex phenomenology of In Vessel Corium Retention (...
Reactor safety experiments for studying the reactions of a molten core (corium) with water and/or co...
The DISCO-H experiments simulate melt ejection scenarios under low system pressure in severe acciden...
In-vessel melt retention is a vital safety design that is incorporated in some nuclear reactors to p...