Werkstoffkennwerte zur Beurteilung der Bruchsicherheit von Kernreaktordruckbeh&@228;ltern

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dc.contributor.author E. Klausnitzer
dc.date.accessioned 2016-10-10T18:46:28Z
dc.date.available 2016-10-10T18:46:28Z
dc.date.issued 1971-09-20T00:00:00+00:00
dc.identifier.uri http://www.lib.ncsu.edu/resolver/1840.20/29007
dc.publisher IASMiRT
dc.relation.ispartofseries G - Steel Pressure Vessels
dc.relation.ispartofseries G5 - Fracture Mechanics Analysis of Steel Reactor Pressure Vessels: Materials Behaviour
dc.relation.ispartofseries SMiRT 1 - Berlin, Germany. September 20-24, 1971
dc.title Werkstoffkennwerte zur Beurteilung der Bruchsicherheit von Kernreaktordruckbeh&@228;ltern
dc.type Conference Proceeding


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