Reactor Vessel Support Asymmetric Loads Analysis for Operating Nuclear Plants

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dc.contributor.authorR.P. Kassawara
dc.contributor.authorJ.J. LaRussa
dc.contributor.authorC.R. Schmidt
dc.date.accessioned2024-07-31T14:00:07Z
dc.date.available2024-07-31T14:00:07Z
dc.date.issued1981-08-17
dc.identifier.urihttps://www.lib.ncsu.edu/resolver/1840.20/42277
dc.publisherIASMiRT
dc.relation.ispartofseriesF - Structural Analysis of Thermal Reactor Core and Coolant Circuit Structure
dc.relation.ispartofseriesF-F8 - Piping : Rupture
dc.relation.ispartofseries00 - SMiRT 6 - Paris, France. August 17-21, 1981
dc.titleReactor Vessel Support Asymmetric Loads Analysis for Operating Nuclear Plants
dc.typeConference Proceeding

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1981 - SMiRT 6 - Paris, France