Preliminary Analysis of the Effect of Fatigue Loading and Crack Propagation on Crack Acceptance Criteria for Nuclear Power Plant Components

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dc.contributor.authorW.F. Anderson
dc.contributor.authorE.C. Johns
dc.date.accessioned2024-07-31T14:00:05Z
dc.date.available2024-07-31T14:00:05Z
dc.date.issued1981-08-17
dc.identifier.urihttps://www.lib.ncsu.edu/resolver/1840.20/42261
dc.publisherIASMiRT
dc.relation.ispartofseriesF - Structural Analysis of Thermal Reactor Core and Coolant Circuit Structure
dc.relation.ispartofseriesF-F6 - Piping: Fatigue
dc.relation.ispartofseries00 - SMiRT 6 - Paris, France. August 17-21, 1981
dc.titlePreliminary Analysis of the Effect of Fatigue Loading and Crack Propagation on Crack Acceptance Criteria for Nuclear Power Plant Components
dc.typeConference Proceeding

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1981 - SMiRT 6 - Paris, France