Abstract
The nal isotopic composition of spent nuclear fuel (SNF) of the RBMK-1500 reactor depends on the initial enrichment of nuclear fuel, reactor performance parameters, fuel burnup and cooling time. Consequently, different SNF results in different radiation characteristics of the CONSTOR and CASTOR containers, where SNF is temporarily stored. Modelling of nuclide composition and its axial distribution along the fuel channel is done using the Monteburns code system. The MCNP5 code was used for the evaluation of radiation shielding and the surface dose rate of the CASTOR cask. The neutron and gamma spectra for MCNP5 source input are calculated with the ORIGEN-ARP code. The modelling results are compared with existing experimental data of the representative container leading to satisfactory agreement. This result proves the validation of calculation methodology for the radiation shielding safety assessment of CASTOR and similar containers used for the storage of RBMK-1500 SNF.
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