Analysis of the Loading of the PWR Reactor Control Rod Elements in Operating Conditions

Simple item page
dc.contributor.authorJ.C. Leroux
dc.contributor.authorB. Grattier
dc.date.accessioned2016-10-10T18:41:23Z
dc.date.available2016-10-10T18:41:23Z
dc.date.issued1983-08-22T00:00:00+00:00
dc.identifier.urihttp://www.lib.ncsu.edu/resolver/1840.20/25856
dc.publisherIASMiRT
dc.relation.ispartofseriesC - Structural Analysis of Fuel, Cladding and Assemblies
dc.relation.ispartofseriesC6 - Thermal Reactor Fuel Assemblies and Core Components
dc.relation.ispartofseriesSMiRT 7 - Chicago, USA. August 22-26, 1983
dc.titleAnalysis of the Loading of the PWR Reactor Control Rod Elements in Operating Conditions
dc.typeConference Proceeding

Files

Original bundle

Now showing 1 - 1 of 1
No Thumbnail Available
Name:
C6-3.pdf
Size:
493.15 KB
Format:
Adobe Portable Document Format
Download

Collections

1983 - SMiRT 7 - Chicago, USA