Abstract
Analysis of the strength of the reactor pressure vessel (RPV) was conducted based on the mechanical strength of the pressure vessel of the Experimental Power Reactor (RDE) and the analysis refers to the design data from the HTR-10 high temperature reactor tank. The RPV design should be capable of ensuring the safety of RDE operation where the reactor pressure vessel will be located. Helium gas is used as a cooling medium for RDE core. The flow of helium gas in a pressure vessel was flowing through the gap between the spheres up to 700 °C and cold helium gas (250 °C) flowing from the outlet nozzle to the nozzle input which causes material degradation due to temperature differences. Analysis of material strength is based on the calculation of stress from the temperature load. Calculation of distribution temperature uses self –developed code based on finite element method and the specification of pressure vessel material was used ASME SA516-70. The results of the calculations are presented in the form of temperature distributions in the form of contours and stress distributions in tabular form. The evaluation of the strength of the material with the temperature difference occurring in the pressure vessel shows stress due to temperature still below the ASME SA516-70 tensile strength limit. However, the stress allowed under ASME Boiler and Pressure is 1/3 of the ASME SA516-70 tensile strength value. The stress calculation that meets the ASME SA516-70 criteria is 192 MPa at an inlet temperature close to 400 °C and an output temperature of 350 °C, respectively. This result can be used as a reference for the basic design of RDE pressure vessel.
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