Abstract
Abstract Analysis has been done for accidental release of radioactive gases from high and low enriched fuel of miniature neutron source reactors (MNSR). Calculations have been performed for existing high enriched uranium (HEU) fuelled core and prospected low enriched uranium (LEU) fuelled core. Composition of existing HEU fuel is UAl4-Al while prospected LEU fuel is UO2. The ORIGEN2 code has been used for burn up and source term calculations. The “Hotspot” version 2.06 has been employed for radiological dispersion analysis to model the release of radioactivity in case of accident. Site specific meteorological data has been employed to determine the dose values for different stability classes as a function of downwind distance. In case of a radiological accident releasing radioactive gases at ground level, the maximum Total Effective Dose Equivalent (TEDE) is about 0.26 Sv for the most prevailing meteorological conditions at the site. There were no appreciable differences found in doses for HEU and LEU fuel.
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