Analysis of Prestressed Concrete Reactor Vessels Under High Thermal Gradient

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dc.contributor.authorP. Gülkan
dc.contributor.authorH.U. Akay
dc.date.accessioned2016-10-10T18:45:14Z
dc.date.available2016-10-10T18:45:14Z
dc.date.issued1975
dc.identifier.urihttp://www.lib.ncsu.edu/resolver/1840.20/28323
dc.publisherIASMiRT
dc.relation.ispartofseriesH - Structural Analysis of Prestressed Concrete Reactor Pressure Vessels
dc.relation.ispartofseriesH2 - Structural Analysis I
dc.relation.ispartofseriesSMiRT 3 - London, UK. 1975
dc.titleAnalysis of Prestressed Concrete Reactor Vessels Under High Thermal Gradient
dc.typeConference Proceeding

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1975 - SMiRT 3 - London, UK