Abstract
For long times there has been a sustained international interest in partitioning and transmutation of spent fuel produced by fission reactors, in particular both plutonium (Pu) and minor actinides (MA), which are associated with nuclear proliferation risks and radioactivity hazards. Transmutation requires the Pu and MA to be irradiated in a very intense neutron flux that can only be attained in a high power fission system such as a thermal reactor, a fast reactor or an accelerator driven system (ADS). The present work investigated two proposed models of core design of different Pu and MA distribution (uniform and nonuniform) applied to TRIGA Mark II ADS reactor to maximize fuel utilization, covering energy extraction and Pu/MA mass reduction. Transmutation performance was studied through burnup and mass ratio time evolution calculations of fuel and minor actinides various components including U, Pu, Am and Cm isotopes, up to two years operation cycle using MCNPX Transport code.
Published Version
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