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: Symposium Paper
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
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.