The DEBRIS Late Phase Melt Progression Model is an assembly of models, embodied in a computer code, which is designed to treat late-phase melt progression in dry rubble (or debris) regions that can form as a consequence of a severe core uncover accident in a commercial light water nuclear reactor. The approach is fully two-dimensional, and incorporates a porous medium modeling framework together with conservation and constitutive relationships to simulate the time-dependent evolution of such regions as various physical processes act upon the materials. The objective of the code is to accurately model these processes so that the late-phase melt progression that would occur in different hypothetical severe nuclear reactor accidents can be bet...
International audienceA hypothetical severe accident in a nuclear power plant has the potential for ...
DoctorMultiphase flow through porous media has been investigated widely in various research fields s...
In the aftermath of the Fukushima Dai-Ichi nuclear accident, the issue of corium coolability has rec...
Designs are described for implementing models for calculating the movement of melted material throug...
A model is described for the movement of melted metallic material through a ceramic porous debris be...
This paper describes a simple fuel melt slumping model to replace the current parametric model in SC...
During a severe nuclear accident, a part of the molten corium resulting from the core degradation ma...
In the late in-vessel phase of a nuclear reactor severe accident, the internal heat transfer and cru...
Designs are described for implementing models for calculating the heat transfer and flow losses in p...
Designs are described for implementing models for calculating the heat transfer and flow losses in p...
The major aim of work in the SARNET2 European project on ex-vessel debris formation and coolability ...
After core meltdown of the sodium-cooled fast reactor (SFR), the jet of molten corium interacts with...
Nordic Boiling Water Reactors (BWRs) employ ex-vessel debris coolability as a severe accident manage...
International audienceIn case of accident at a nuclear power plant, water sources may not be availab...
International audienceThis paper is a study of debris beds that can form in the core of a nuclear po...
International audienceA hypothetical severe accident in a nuclear power plant has the potential for ...
DoctorMultiphase flow through porous media has been investigated widely in various research fields s...
In the aftermath of the Fukushima Dai-Ichi nuclear accident, the issue of corium coolability has rec...
Designs are described for implementing models for calculating the movement of melted material throug...
A model is described for the movement of melted metallic material through a ceramic porous debris be...
This paper describes a simple fuel melt slumping model to replace the current parametric model in SC...
During a severe nuclear accident, a part of the molten corium resulting from the core degradation ma...
In the late in-vessel phase of a nuclear reactor severe accident, the internal heat transfer and cru...
Designs are described for implementing models for calculating the heat transfer and flow losses in p...
Designs are described for implementing models for calculating the heat transfer and flow losses in p...
The major aim of work in the SARNET2 European project on ex-vessel debris formation and coolability ...
After core meltdown of the sodium-cooled fast reactor (SFR), the jet of molten corium interacts with...
Nordic Boiling Water Reactors (BWRs) employ ex-vessel debris coolability as a severe accident manage...
International audienceIn case of accident at a nuclear power plant, water sources may not be availab...
International audienceThis paper is a study of debris beds that can form in the core of a nuclear po...
International audienceA hypothetical severe accident in a nuclear power plant has the potential for ...
DoctorMultiphase flow through porous media has been investigated widely in various research fields s...
In the aftermath of the Fukushima Dai-Ichi nuclear accident, the issue of corium coolability has rec...