A Simplified Method of Inelastic Analysis for the Design of Sodium Cooled Fast Reactor Vessels

Show simple item record

dc.contributor.author A. Pellissier-Tanon
dc.date.accessioned 2016-10-10T18:45:47Z
dc.date.available 2016-10-10T18:45:47Z
dc.date.issued 1973-09-10T00:00:00+00:00
dc.identifier.uri http://www.lib.ncsu.edu/resolver/1840.20/28631
dc.publisher IASMiRT
dc.relation.ispartofseries G - Structural Analysis of Steel Reactor Vessels
dc.relation.ispartofseries G1 - Stress Analysis and Design of Reactor Vessels--I
dc.relation.ispartofseries SMiRT 2 - Berlin, Germany. September 10-14, 1973
dc.title A Simplified Method of Inelastic Analysis for the Design of Sodium Cooled Fast Reactor Vessels
dc.type Conference Proceeding


Files in this item

Files Size Format View
G1-6.pdf 380.6Kb PDF View/Open

This item appears in the following Collection(s)

Show simple item record