This article gives an overview of the severe accident research as part of the reactor safety programme at JRC-ITU Karlsruhe. ITU has been examining the high temperature properties of U-Zr-Fe-O materials fabricated in the institute using a laser heating and pyrometry system to observe the various melting transitions. It has also examined selected ex-vessel compositions. The paper then describes samples taken from major severe accident studies including the melted material from TMI-2 and degraded bundles from the French IRSN Phébus PF project. The comparison of the small and large-scale studies illustrate how the similar processes are observed and how the small scale testing can help understanding of reactor core degradation. In particular th...
The core loss during a severe accident (COLOSS) project was a 3-year shared-cost action, which start...
The Phébus PF project is an international programme examining the release behaviour of fission produ...
The problem of irradiated fuel (both UO2 & Mixed Oxide Fuels) interactions with liquefied Zircaloy a...
During a severe nuclear accident, the UO2 fuel rods, Zircaloy cladding, guide tubes, absorber and st...
The early stages of a severe accident are characterised by a loss of cooling capability in the react...
With the current situation in Japan it is worthwhile to examine previous research into severe accide...
With the current situation in Japan one should examine previous research into severe accidents and t...
Nuclear safety research programmes in the European Commission's Joint Research Centre cover aspects ...
International audienceThe international Phébus Fission Product Programme investigated key phenomena ...
<p>Major and severe accidents have occurred three times in nuclear power plants (NPPs), at Three Mil...
Within the Generation IV International Forum (GIF), considerable efforts are devoted in Europe to re...
International audienceOne objective of the FPT2 test of the PHEBUS FP Program was to study the degra...
International audienceReactor core degradation and in-vessel and ex-vessel corium behavior have been...
International audienceSevere accident with core meltdown is a threat to the containment integrity. A...
Four spherical high-temperature reactor fuel elements irradiated at the High Flux Reactor in Petten ...
The core loss during a severe accident (COLOSS) project was a 3-year shared-cost action, which start...
The Phébus PF project is an international programme examining the release behaviour of fission produ...
The problem of irradiated fuel (both UO2 & Mixed Oxide Fuels) interactions with liquefied Zircaloy a...
During a severe nuclear accident, the UO2 fuel rods, Zircaloy cladding, guide tubes, absorber and st...
The early stages of a severe accident are characterised by a loss of cooling capability in the react...
With the current situation in Japan it is worthwhile to examine previous research into severe accide...
With the current situation in Japan one should examine previous research into severe accidents and t...
Nuclear safety research programmes in the European Commission's Joint Research Centre cover aspects ...
International audienceThe international Phébus Fission Product Programme investigated key phenomena ...
<p>Major and severe accidents have occurred three times in nuclear power plants (NPPs), at Three Mil...
Within the Generation IV International Forum (GIF), considerable efforts are devoted in Europe to re...
International audienceOne objective of the FPT2 test of the PHEBUS FP Program was to study the degra...
International audienceReactor core degradation and in-vessel and ex-vessel corium behavior have been...
International audienceSevere accident with core meltdown is a threat to the containment integrity. A...
Four spherical high-temperature reactor fuel elements irradiated at the High Flux Reactor in Petten ...
The core loss during a severe accident (COLOSS) project was a 3-year shared-cost action, which start...
The Phébus PF project is an international programme examining the release behaviour of fission produ...
The problem of irradiated fuel (both UO2 & Mixed Oxide Fuels) interactions with liquefied Zircaloy a...