Introduction

Abstract

This paper illustrates the work carried out by EDF within the framework of ISP 48 post-test analysis of NUPEC/NRC 1:4-scale model of a prestressed pressure containment vessel of a nuclear power plant [Hessheimer, M.F., Klamerus, E.W., Rightly, G.S., Lambert, L.D., Dameron, R.A., 2003. Overpressurization test of a 1:4-scale prestressed concrete containment vessel model. NUREG/CR-6810, SAND2003-0840P. Sandia National Laboratories, Albuquerque, NM]. EDF as a participant of the International Standard Problem no. 48 [Mathet, E., Hessheimer, M., Ali, S., Tegeler, B., 2005. An international standard problem: analysis of 1:4-scale prestressed concrete containment vessel model under severe accident conditions. Proceedings of 18th International Conference on Structural Mechanics in Reactor Technology. SMiRT 18. Beijing, China] has participated in this program, within the framework of its research and development program on the simulation of non-linear behaviour of nuclear power plant prestressed concrete pressure containment vessels. EDF performed several simulations to determine the ultimate response of the scale model. To determine the most influent parameters in such an analysis several studies were carried out. A full 3D mesh of the entire structure was then created. The mesh was built using a parametric tool to measure the influence of discretization on results. To represent the cracking of concrete, two material laws were then used. The purpose of this paper is to illustrate the ultimate behaviour of SANDIA II model obtained by Code_Aster® finite element platform, with comparison to tests records, and also to share the lessons learned from the parametric computations and underline precautions that must be taken in such studies.