Creep Behavior Under Sustained Temperature Gradient in a Model of Prestressed Concrete Reactor Vessels

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Title: Creep Behavior Under Sustained Temperature Gradient in a Model of Prestressed Concrete Reactor Vessels
Author: H. Ohnuma; Y. Aoyagi; H. Abe
Publisher: IASMiRT
Date: 1979
Series/Report No.: H - Structural Engineering of Prestressed Reactor Pressure Vessels
H4 - Structural Analysis of PCVs and Components
SMiRT 5 - Berlin, Germany. 1979
URI: http://www.lib.ncsu.edu/resolver/1840.20/26671


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