Behaviour of a Prestressed Reactor Pressure Vessel for HTR Under Extremely High Core Temperature Loading

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dc.contributor.authorJ. Altes
dc.contributor.authorU. Schneider
dc.contributor.authorK. Schimmelpfennig
dc.date.accessioned2024-07-31T14:00:18Z
dc.date.available2024-07-31T14:00:18Z
dc.date.issued1981-08-17
dc.identifier.urihttps://www.lib.ncsu.edu/resolver/1840.20/42344
dc.publisherIASMiRT
dc.relation.ispartofseriesH - Structural Engineering of Prestressed Reactor Pressure Vessels
dc.relation.ispartofseriesH-H2 - Trends in Design, Research, and Application of PCVs
dc.relation.ispartofseries00 - SMiRT 6 - Paris, France. August 17-21, 1981
dc.titleBehaviour of a Prestressed Reactor Pressure Vessel for HTR Under Extremely High Core Temperature Loading
dc.typeConference Proceeding

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1981 - SMiRT 6 - Paris, France