Finite element analysis on reactor pressure vessel support lug for RDE

Abstract

Reaktor Daya Eksperimental (RDE) is a demonstration nuclear plant with type of a pebble bed core. Reactor pressure vessel (RPV) for RDE core is designed to hold helium under pressure of 3 MPa and temperature of 250 °C. RPV is supported by four support lugs for subjecting to the occurred stresses close to interface area. An accurate calculation and analysis of the stresses and displacements of the RPV is thus of great importance. Objective of present paper is to calculate and to analyse the stresses distribution of the RPV support lugs for RDE. In calculation and analysis, model of RPV support lug is simulated by using software program of SolidWorks, and derived into static type and solid mesh. Finite element method is applied to calculate the stresses distribution of support lugs input data such as temperature, pressure, loads, and so on for CP-Ti Grade-4 SS material. Results show that the RPV support lugs can be considered to have met the safety requirements of ASME in Section III with the FOS value of 1000. Calculation results obtained for maximum values of stresses are Hoop stress of 126.025 MPa, axial stress of 116.108 MPa, radial stress of 45.1338 MPa, and von Mises stress of 242.934 MPa. It is concluded that RPV support lugs are properly used for the RDE.