Theoretical Analysis of Stress, Strain and Fracture of Fast Reactor Fuel Cladding under Constant Power and Power-Cycling Conditions: Visco-elastic Model of Nuclear Fuel-pin Behavior

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dc.contributor.authorJ.H. Gittus
dc.date.accessioned2016-10-10T18:45:37Z
dc.date.available2016-10-10T18:45:37Z
dc.date.issued1973-09-10T00:00:00+00:00
dc.identifier.urihttp://www.lib.ncsu.edu/resolver/1840.20/28530
dc.publisherIASMiRT
dc.relation.ispartofseriesC - Structural Analysis of Reactor Fuel and Cladding
dc.relation.ispartofseriesC2 - Structural Analysis of Fuel Element Cladding--I
dc.relation.ispartofseriesSMiRT 2 - Berlin, Germany. September 10-14, 1973
dc.titleTheoretical Analysis of Stress, Strain and Fracture of Fast Reactor Fuel Cladding under Constant Power and Power-Cycling Conditions: Visco-elastic Model of Nuclear Fuel-pin Behavior
dc.typeConference Proceeding

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