Fatigue and Fracture Analysis of Reactor Pressure Vessels According to French Rules RCC-M

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dc.contributor.authorP. Collet
dc.contributor.authorTh. Foult
dc.contributor.authorC. Faidy
dc.date.accessioned2016-10-10T18:41:36Z
dc.date.available2016-10-10T18:41:36Z
dc.date.issued1983-08-22T00:00:00+00:00
dc.identifier.urihttp://www.lib.ncsu.edu/resolver/1840.20/26009
dc.publisherIASMiRT
dc.relation.ispartofseriesG - LWR Pressure Components - Vessels
dc.relation.ispartofseriesG1 - Integrity Assessment
dc.relation.ispartofseriesSMiRT 7 - Chicago, USA. August 22-26, 1983
dc.titleFatigue and Fracture Analysis of Reactor Pressure Vessels According to French Rules RCC-M
dc.typeConference Proceeding

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1983 - SMiRT 7 - Chicago, USA