ANALYSIS OF THE KRŠKO NPP SPENT FUEL STORAGE CRITICALITY SAFETY UNDER HYPOTHETICAL DEGRADED CONDITIONS
Abstract
An analysis of the Krško NPP’s old racks under hypothetical degraded pool conditions has been performed. Pool boiling and the optimum neutron moderation scenario with the absence of soluble boron normally present in the cooling water have been analysed. MCNP neutron transport code version 6.1.0 and the neutron continuous energy cross section ACE library based on the ENDF/B- VII.1 nuclear data files have been used. Four out of four and three out of four cell positions loaded have been considered. Where appropriate, burnup curves were determined.
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References
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