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 reactor pressure vessel (RPV) the possible failure modes of the RPV and the time to failure have to be investigated to assess the po...

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Bibliographic Details
Main Author: Willschütz, Hans-Georg
Other Authors: Technische Universität Dresden, Maschinenwesen
Format: Doctoral Thesis
Language:deu
Published: Saechsische Landesbibliothek- Staats- und Universitaetsbibliothek Dresden 2006
Subjects:
Online Access:http://nbn-resolving.de/urn:nbn:de:swb:14-1138712734373-55289
http://nbn-resolving.de/urn:nbn:de:swb:14-1138712734373-55289
http://www.qucosa.de/fileadmin/data/qucosa/documents/1439/1138712734373-5528.pdf

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