Fatigue Analysis on the Internals of Qinshan 600Mwe Nuclear Reactor in Flow-lnduced Vibration Test Using the Extreme Value Distribution Method

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dc.contributor.authorLiang Zhijian
dc.contributor.authorHu Yongtao
dc.date.accessioned2016-10-10T18:48:13Z
dc.date.available2016-10-10T18:48:13Z
dc.date.issued1999-08-15T00:00:00+00:00
dc.identifier.urihttp://www.lib.ncsu.edu/resolver/1840.20/30208
dc.publisherIASMiRT
dc.relation.ispartofseriesJ - Structural Dynamics and Extreme Load Analysis
dc.relation.ispartofseriesJ01 -
dc.relation.ispartofseriesSMiRT 15 - Seoul, South Korea. August 15-20, 1999
dc.titleFatigue Analysis on the Internals of Qinshan 600Mwe Nuclear Reactor in Flow-lnduced Vibration Test Using the Extreme Value Distribution Method
dc.typeConference Proceeding

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1999 - SMiRT 15 - Seoul, South Korea