Title of article
Investigations on the phenomenology of ex-vessel core melt behaviour (COMAS)
Author/Authors
Fischer، M. نويسنده , , Steinwarz، W. نويسنده , , Alemberti، A. نويسنده , , Hafner، W. نويسنده , , Alkan، Z. نويسنده ,
Issue Information
دوهفته نامه با شماره پیاپی سال 2001
Pages
-138
From page
139
To page
0
Abstract
Within the COMAS (corium on material surfaces) project, representative experimental and analytical investigations on the ex-vessel spreading behaviour of prototypic corium were performed to provide a realistic technical basis for the development of core catchers for future nuclear reactor generations. In various large-scale experiments, melts in the Mg-range with real corium compositions and temperatures around 2000 °C were tested using different substratum materials (concrete, ceramics, cast iron). These tests were carried out at Siempelkampʹs CARLA melting facility for radioactively contaminated metal scrap supported by laboratory experiments at Siemens, Erlangen. The COMAS results indicate that for a sufficiently high melt release rate a quick and homogeneous coverage of an ex-vessel spreading compartment as realized in the Franco-German EPR project can be expected. Regarding the analytical assessment, it can be concluded that some spreading codes have reached a sufficient level to provide guidelines for the evaluation of spreading concepts. Open questions are mainly related to segregation and immobilization of the melt.
Keywords
Euratom Framework Programme , Operational safety of existing installations , Plant life extension and management (PLEM) , Severe accident management (SAM) and evolutionary concepts (EVOL) , Key action Nuclear Fission
Journal title
Nuclear Engineering and Design
Serial Year
2001
Journal title
Nuclear Engineering and Design
Record number
13600
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