Status of the development of the FINAS inelastic structural analysis system for FBR

Since high security is generally required for nuclear power plants, the detailed structural analysis has been implemented. In fact breeder reactors, more detailed analysis is required because their higher operating temperature (over 500 deg C) than light water reactors necessitates the design in inelastic region considering the plastic and creep characteristics of structural materials. FBR Inelastic Structural Analysis System,FINAS, introduced in this paper, is a computer program using the finite element method, which has been developed by the structural material developing group in the FBR Project, Power Reactor and Nuclear Fuel Development Corp. (PNC), in cooperation with the Century Research Center Co., Ltd. FINAS has nearly completed the initial schedule of development in 5 years until June, 1981, and presently installed in the computer room of Oarai Engineering Center, PNC. It is still subjected to the improvement and adjustment of the program. In this paper, the outline of the system and the summary of analytical method are described after explaining the background and progress of the development of the program. As the examples of FINAS application, the following are given: the thermal ratchet of a cylinder, a problem of a disk subjected to forced displacement hysteresis, a problem of liquid sodium level fluctuation, the analysis of an elbow, the analysis of stress in a three-dimensional piping system, and the seismic response analysis for a beam model in a multi-material point system. (Wakatsuki, Y.)