Fracture of Zircaloy Cladding as a Consequence of Power Increases in Water Reactor Fuel Rods

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dc.contributor.authorG. V. Ranjan
dc.contributor.authorE. Smith
dc.date.accessioned2016-10-10T18:43:55Z
dc.date.available2016-10-10T18:43:55Z
dc.date.issued1977
dc.identifier.urihttp://www.lib.ncsu.edu/resolver/1840.20/27489
dc.publisherIASMiRT
dc.relation.ispartofseriesC - Structural Analysis of Reactor Fuel and Cladding
dc.relation.ispartofseriesC2 - Modeling and Analyses II
dc.relation.ispartofseriesSMiRT 4 - San Francisco, USA. 1977
dc.titleFracture of Zircaloy Cladding as a Consequence of Power Increases in Water Reactor Fuel Rods
dc.typeConference Proceeding

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1977 - SMiRT 4 - San Francisco, USA