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
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
DOI:
10.14359/18065
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.