Degradation and oxidation of B4C control rod segments at high temperatures. A review and code interpretation of the BECARRE program

The paper gives a code-based interpretation of the experimental BECARRE program carried out at the “Institut de Radioprotection et de Sureté Nucléaire” (IRSN) between 2005 and 2010, using the severe accident (SA) code ASTEC/ICARE. As part of the International Source Term Program (ISTP), the BECARRE...

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Veröffentlicht in:	Nuclear engineering and design 2013-06, Vol.259, p.150-165
1. Verfasser:	de Luze, O.
Format:	Artikel
Sprache:	eng
Schlagworte:	Bearing Carbon dioxide Carbon monoxide Control rods Degradation Failure Melts Nuclear engineering Oxidation Pellets Physics Pressurized water reactors Segments
Online-Zugang:	Volltext
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