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

Show simple item record

dc.contributor.author J.H. Gittus
dc.date.accessioned 2016-10-10T18:45:37Z
dc.date.available 2016-10-10T18:45:37Z
dc.date.issued 1973-09-10T00:00:00+00:00
dc.identifier.uri http://www.lib.ncsu.edu/resolver/1840.20/28530
dc.publisher IASMiRT
dc.relation.ispartofseries C - Structural Analysis of Reactor Fuel and Cladding
dc.relation.ispartofseries C2 - Structural Analysis of Fuel Element Cladding--I
dc.relation.ispartofseries SMiRT 2 - Berlin, Germany. September 10-14, 1973
dc.title 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
dc.type Conference Proceeding


Files in this item

Files Size Format View
C2-1.pdf 222.4Kb PDF View/Open

This item appears in the following Collection(s)

Show simple item record