Lumped-parameter Analysis of Cylindrical prestressed Concrete Reactor Vessels

The use of nuclear energy in the production of electrical power involves substantial structural systems comprised of pressure and containment vessels that house the nuclear reactor. Efficient operation of a nuclear plant requires a large electrical output. This requirement means structures of sizable dimensions. The object of this study is the development of a mathematical procedure suitable for the analysis of prestressed concrete pressure vessels in both the elastic and inelastic ranges. It has been found that a lumped parameter approach offers a number of advantages in the treatment of localized inelastic behavior. The analogue used here is an extension of the lumped parameter model developed at the University of Illinois. The model was initially used for a study of contained plastic flow problems.Part of the Prestressed Concrete Reactor Vessel Program of the Oak Ridge National Laboratory, operated by Union Carbide Corp. for the U.S. Atomic Energy Commission. Subcontract no. 2906 under Contract no. W-7405-eng-26