Experimental Study of the Behavior of the Prestressed Concrete Reactor Pressure Vessel of the THTR-300 At Severe Accident Temperatures

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dc.contributor.authorA. Jurgen
dc.contributor.authorK.H. Escherich
dc.contributor.authorM. Nickel
dc.contributor.authorJ. Wolters
dc.date.accessioned2016-10-10T18:37:36Z
dc.date.available2016-10-10T18:37:36Z
dc.date.issued1991-08-18T00:00:00+00:00
dc.identifier.urihttp://www.lib.ncsu.edu/resolver/1840.20/23167
dc.publisherIASMiRT
dc.relation.ispartofseriesH - Concrete and Concrete Structures
dc.relation.ispartofseriesH03 - Temperature Effect (II)
dc.relation.ispartofseriesSMiRT 11 - Tokyo, Japan. August 18-23, 1991
dc.titleExperimental Study of the Behavior of the Prestressed Concrete Reactor Pressure Vessel of the THTR-300 At Severe Accident Temperatures
dc.typeConference Proceeding

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1991 - SMiRT 11 - Tokyo, Japan