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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Title: A Hypothetical Accident of a Sodium Cooled Fast Breeder Reactor as a Basis for the Design of a Prismatic Concrete Containment System
Author: L. Lange; H. Laue
Publisher: IASMiRT
Date: 1971-09-20
Series/Report No.: J - Analysis of Shell Structures: Containment
J3 - Containment of Power Reactor Plants - I
SMiRT 1 - Berlin, Germany. September 20-24, 1971
URI: http://www.lib.ncsu.edu/resolver/1840.20/29083


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