Radiological safety analysis of the SAMOP reactor experimental facility

Abstract

The reactor subcritical assembly for 99Mo production (SAMOP) experimental facility is a nuclear reactor operating under subcritical conditions. SAMOP reactor is fueled by uranyl nitrate inside an annular tube surrounded by the TRIGA reactor fuels. The external neutron source required for the SAMOP reactor operation comes from the Kartini reactor radial beam-port. The aim of the analysis is to determine the estimated personnel radiation dose for normal conditions and severe postulated accident. The analysis methods is a calculation of source term, radiation propagation to the surrounding area, and estimation of personnel radiation dose rate for normal and severe accident conditions. The analysis result shows that the effective radiation dose received by personnel in the working area of the SAMOP reactor is below the dose limit for radiation worker at the Kartini reactor, i.e. 7 μSv/h. Whereas, in the postulated severe accident condition, the highest exposure rate at 1 m above and beside the reactor cooling tank are 4.19 mSv/h and 1.35 mSv/h respectively.