Design Criteria for Calculation Code of a Hot Channel in a Pressure Tube Nuclear Reactor

Simple item page
dc.contributor.authorJ. Bernard
dc.contributor.authorJ. Dufresne
dc.contributor.authorF. Farfaletti-Casali
dc.contributor.authorJ. Putzeys
dc.date.accessioned2016-10-10T18:46:25Z
dc.date.available2016-10-10T18:46:25Z
dc.date.issued1971-09-20T00:00:00+00:00
dc.identifier.urihttp://www.lib.ncsu.edu/resolver/1840.20/28973
dc.publisherIASMiRT
dc.relation.ispartofseriesF - Structural Analysis of Core Support and Coolant Circuit Structures
dc.relation.ispartofseriesF4 - Structural Analysis of Coolant Circuit Components- II
dc.relation.ispartofseriesSMiRT 1 - Berlin, Germany. September 20-24, 1971
dc.titleDesign Criteria for Calculation Code of a Hot Channel in a Pressure Tube Nuclear Reactor
dc.typeConference Proceeding

Files

Original bundle

Now showing 1 - 1 of 1
No Thumbnail Available
Name:
F4-2.pdf
Size:
193.69 KB
Format:
Adobe Portable Document Format
Download

Collections

1971 - SMiRT 1 - Berlin, Germany