A Hypothetical Accident of a Sodium Cooled Fast Breeder Reactor as a Basis for the Design of a Prismatic Concrete Containment System

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dc.contributor.authorL. Lange
dc.contributor.authorH. Laue
dc.date.accessioned2016-10-10T18:46:36Z
dc.date.available2016-10-10T18:46:36Z
dc.date.issued1971-09-20T00:00:00+00:00
dc.identifier.urihttp://www.lib.ncsu.edu/resolver/1840.20/29083
dc.publisherIASMiRT
dc.relation.ispartofseriesJ - Analysis of Shell Structures: Containment
dc.relation.ispartofseriesJ3 - Containment of Power Reactor Plants - I
dc.relation.ispartofseriesSMiRT 1 - Berlin, Germany. September 20-24, 1971
dc.titleA Hypothetical Accident of a Sodium Cooled Fast Breeder Reactor as a Basis for the Design of a Prismatic Concrete Containment System
dc.typeConference Proceeding

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1971 - SMiRT 1 - Berlin, Germany