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

Simple item page
dc.contributor.authorA. Pellissier-Tanon
dc.date.accessioned2016-10-10T18:45:47Z
dc.date.available2016-10-10T18:45:47Z
dc.date.issued1973-09-10T00:00:00+00:00
dc.identifier.urihttp://www.lib.ncsu.edu/resolver/1840.20/28631
dc.publisherIASMiRT
dc.relation.ispartofseriesG - Structural Analysis of Steel Reactor Vessels
dc.relation.ispartofseriesG1 - Stress Analysis and Design of Reactor Vessels--I
dc.relation.ispartofseriesSMiRT 2 - Berlin, Germany. September 10-14, 1973
dc.titleA Simplified Method of Inelastic Analysis for the Design of Sodium Cooled Fast Reactor Vessels
dc.typeConference Proceeding

Files

Original bundle

Now showing 1 - 1 of 1
No Thumbnail Available
Name:
G1-6.pdf
Size:
380.61 KB
Format:
Adobe Portable Document Format
Download

Collections

1973 - SMiRT 2 - Berlin, Germany