Generation of a High Temperature Material Data Base and its Application to Creep Tests with French or German RPV-steel
Considering the hypothetical core melt down scenario for a light water reactor (LWR) a possible failure mode of the reactor pressure vessel (RPV) and its failure time has to be investigated for a determination of the loadings on the containment. Numerous experiments have been performed accompanied w...
| Main Authors: | , |
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| Format: | Others |
| Language: | English |
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Forschungszentrum Dresden
2010
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| Online Access: | http://nbn-resolving.de/urn:nbn:de:bsz:d120-qucosa-29413 http://nbn-resolving.de/urn:nbn:de:bsz:d120-qucosa-29413 http://www.qucosa.de/fileadmin/data/qucosa/documents/2941/4583.pdf |