Thermal Response Analysis of the Three Mile Island Unit 2 Reactor Pressure Vessel

Simple item page
dc.contributor.authorK. Hashimoto
dc.contributor.authorK. Onizawa
dc.contributor.authorH. Kimura
dc.contributor.authorR. Kurihara
dc.contributor.authorS. Kawasaki
dc.date.accessioned2016-10-10T18:37:22Z
dc.date.available2016-10-10T18:37:22Z
dc.date.issued1991-08-18T00:00:00+00:00
dc.identifier.urihttp://www.lib.ncsu.edu/resolver/1840.20/23001
dc.publisherIASMiRT
dc.relation.ispartofseriesF - Pressure Components, Design Technologies, and Research for Regulatory Needs
dc.relation.ispartofseriesF06 - Structural Integrity Assessment
dc.relation.ispartofseriesSMiRT 11 - Tokyo, Japan. August 18-23, 1991
dc.titleThermal Response Analysis of the Three Mile Island Unit 2 Reactor Pressure Vessel
dc.typeConference Proceeding

Files

Original bundle

Now showing 1 - 1 of 1
No Thumbnail Available
Name:
F06-5.pdf
Size:
253.23 KB
Format:
Adobe Portable Document Format
Download

Collections

1991 - SMiRT 11 - Tokyo, Japan