Discussion of Finite Element Analysis of Prestressed Concrete Reactor Vessels

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Title: Discussion of Finite Element Analysis of Prestressed Concrete Reactor Vessels

Author(s): J.H. Argyris, K.E. Buck, I. Grieger, and K.J. Willam

Publication: Special Publication

Volume: 34

Issue:

Appears on pages(s): 181-202

Keywords: computer programs; finite element method; matrix models; nuclear reactor containment; nuclear reactors; prestressed concrete; shells (structural forms); stresses; structural analysis

Date: 1/1/1972

Abstract:
A discussion is presented on the state-of-the-art of finite element analysis particularly as it applies to the analysis of reactor vessels. The matrix displacement method using the special computer language ASKA as well as a more general approach using FORTRAN IV is presented.