Parametric Thermal-Hydraulic Studies of HTGR Reactor Vessel System - Consequences on the Structure Lifetime

Simple item page
dc.contributor.authorShengqiang Li
dc.date.accessioned2016-10-10T18:50:25Z
dc.date.available2016-10-10T18:50:25Z
dc.date.issued2005-08-07T00:00:00+00:00
dc.identifier.urihttp://www.lib.ncsu.edu/resolver/1840.20/31847
dc.publisherIASMiRT
dc.relation.ispartofseriesP - Severe Accident Management and Structural Evaluation
dc.relation.ispartofseriesP01 - Modeling and Analysis
dc.relation.ispartofseriesSMiRT 18 - Beijing, China. August 7-12, 2005
dc.titleParametric Thermal-Hydraulic Studies of HTGR Reactor Vessel System - Consequences on the Structure Lifetime
dc.typeConference Proceeding

Files

Original bundle

Now showing 1 - 1 of 1
No Thumbnail Available
Name:
P01_9.pdf
Size:
240.68 KB
Format:
Adobe Portable Document Format
Download

Collections

2005 - SMiRT 18 - Beijing, China