A Model for Fuel Rod and Tie Rod Elongations in Boiling Water Reactor Fuel Bundles

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dc.contributor.authorK.R. Merckx
dc.date.accessioned2016-10-10T18:42:20Z
dc.date.available2016-10-10T18:42:20Z
dc.date.issued1979
dc.identifier.urihttp://www.lib.ncsu.edu/resolver/1840.20/26492
dc.publisherIASMiRT
dc.relation.ispartofseriesD - Structural Analysis of Reactor Fuel Elements and Assemblies
dc.relation.ispartofseriesD4 - Thermal Reactor Subassembly Analysis
dc.relation.ispartofseriesSMiRT 5 - Berlin, Germany. 1979
dc.titleA Model for Fuel Rod and Tie Rod Elongations in Boiling Water Reactor Fuel Bundles
dc.typeConference Proceeding

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1979 - SMiRT 5 - Berlin, Germany