engleski

Analysis of the HI-TRAC VW Transfer Cask Dose Rates During Nuclear Power Plant Krsko Spent Fuel Dry Storage Campaign One

In this paper shielding analysis is performed to establish neutron and gamma dose rates around the transfer cask HI-TRAC VW loaded with Fuel Assemblies (FA) from Nuclear Power Plant Krsko (NEK) Spent Fuel Dry Storage (SFDS) Campaign one. The HI-TRAC VW is a multi-layered cylindrical vessel designed to accept a Multi Purpose Canister (MPC) during loading, unloading and transfer to dry storage building. The MPC can contain up to 37 spent fuel assemblies. The analysis is divided into two steps. The first step is the source term generation using ORIGEN- S SCALE sequence. The source is calculated based on the operating history of spent fuel assemblies currently located in the NEK spent fuel pool. The obtained intensities and spectra of the spent fuel assemblies are used in the second step to calculate the dose rates around the transfer cask. A comprehensive shielding analysis included the calculation of dose rates resulting from fuel neutrons, fuel gammas, neutron induced gammas (n-g reaction), and hardware gammas under normal conditions and during accident scenario. To obtain the dose rates with the acceptable uncertainties, FW- CADIS based variance reduction is adopted, as implemented in ADVANTG code. The dose rates around HI-TRAC VW cask are calculated using MCNP6 code for all 16 casks loading belonging to Campaign one in order to illustrate the impact of fuel assembly selection schemes proposed by company responsible for project realization (Holtec International).

shielding, Monte Carlo, dose rates, cask, SCALE6, MCNP6, ADVANTG

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