Model of Zircaloy Cladding Damage in Pressurized Water Reactors

dc.contributor.authorL. Camin
dc.contributor.authorG. Chaigne
dc.contributor.authorJ. Joseph
dc.date.accessioned2016-10-10T18:37:17Z
dc.date.available2016-10-10T18:37:17Z
dc.date.issued1991-08-18T00:00:00+00:00
dc.identifier.urihttp://www.lib.ncsu.edu/resolver/1840.20/22954
dc.publisherIASMiRT
dc.relation.ispartofseriesC - Fuel and Core Structures
dc.relation.ispartofseriesC02 - Fuel Element Structural Analysis (II)
dc.relation.ispartofseriesSMiRT 11 - Tokyo, Japan. August 18-23, 1991
dc.titleModel of Zircaloy Cladding Damage in Pressurized Water Reactorsen_US
dc.typeConference Proceeding

Files

Original bundle

Now showing 1 - 1 of 1
No Thumbnail Available
Name:
C02-1.pdf
Size:
181.8 KB
Format:
Adobe Portable Document Format