Thermomechanische Modellierung eines Reaktordruckbehälters in der Spätphase eines Kernschmelzunfalls

Thermomechanische Modellierung eines Reaktordruckbehälters in der Spätphase eines Kernschmelzunfalls

Considering the late in-vessel phase of an unlikely core melt down scenario in a light water reactor (LWR) with the formation of a corium pool in the lower head of the re-actor pressure vessel (RPV) the possible failure modes of the RPV and the time to failure have to be investigated to assess the p...

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Bibliographic Details
Main Author:	Willschütz, H.-G.
Other Authors:	Forschungszentrum Rossendorf, Institut für Sicherheitsforschung
Format:	Others
Language:	deu
Published:	Forschungszentrum Dresden 2010
Subjects:	Light Water Reactor severe accident with core melt down In-Vessel-Retention recoursively coupled thermal and mechanical simulation scaled experiments and prototypic scenario
Online Access:	http://nbn-resolving.de/urn:nbn:de:bsz:d120-qucosa-28520 http://nbn-resolving.de/urn:nbn:de:bsz:d120-qucosa-28520 http://www.qucosa.de/fileadmin/data/qucosa/documents/2852/8141.pdf

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