Seismic Analysis of Class-1 Nuclear Components

Abstract

Steam generator are shell and tube heat exchanger use for generating steam in nuclear power plant to generate electricity. In nuclear power plant, each reactor is connected with 4,700 MWe steam generators. Nowadays, pressurized heavy water reactor steam generators are used to generate steam at high temperature and high pressure. Steam generated at high temperature and pressure is used to run turbine. Pressure vessels/Steam Generators are an important equipment for the nuclear, petrochemical and many other industries. The vessels are subjected to various loadings during operating condition and these loads are considered during the pressure vessel design. FE analysis is performed in ANSYS & FEAST software in order to qualify vessel for seismic load as it is one of the important load. Approach used for the FE modelling is a simplied 1D- beam stick approach (equivalent mass modelling & cross section) considering lled condition of the vessel. ASME SECTION III NB provides guidelines for design of nuclear facility components. So design by rule is done by ASME SECTION III NB. For carrying out seismic analysis of the component guidelines are provided in code ASME SECTION III - APPENDICES. Results obtained for standard cantilever beam and 1D beam stick model of dummy vessel were found satisfactory. Further to this real constant approach is found good using which seismic analysis of steam generator is to be performed.