Analysis of Prestressed Concrete Reactor Vessels Under High Thermal Gradient

Show full item record

Title: Analysis of Prestressed Concrete Reactor Vessels Under High Thermal Gradient
Author: P. Gülkan; H.U. Akay
Publisher: IASMiRT
Date: 1975
Series/Report No.: H - Structural Analysis of Prestressed Concrete Reactor Pressure Vessels
H2 - Structural Analysis I
SMiRT 3 - London, UK. 1975
URI: http://www.lib.ncsu.edu/resolver/1840.20/28323


Files in this item

Files Size Format View
H2-4.pdf 323.1Kb PDF View/Open

This item appears in the following Collection(s)

Show full item record