Design and Development of a High Thermal Conductivity Concrete for the Sodium Cooled Fast Reactor

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dc.contributor.authorR. Blundell
dc.contributor.authorS. Kupermann
dc.contributor.authorK. Albeson
dc.contributor.authorW. Blair
dc.date.accessioned2016-10-10T18:42:36Z
dc.date.available2016-10-10T18:42:36Z
dc.date.issued1979
dc.identifier.urihttp://www.lib.ncsu.edu/resolver/1840.20/26691
dc.publisherIASMiRT
dc.relation.ispartofseriesH - Structural Engineering of Prestressed Reactor Pressure Vessels
dc.relation.ispartofseriesH8 - Concept and Research for a PCV for the LMFBR
dc.relation.ispartofseriesSMiRT 5 - Berlin, Germany. 1979
dc.titleDesign and Development of a High Thermal Conductivity Concrete for the Sodium Cooled Fast Reactor
dc.typeConference Proceeding

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1979 - SMiRT 5 - Berlin, Germany