Preliminary Assessment of Radiation Impact from Dry Storage Facilities for PWR Spent Fuel
Kim, T.M.;Baeg, C.Y.;Cha, G.Y.;Lee, W.G.;Kim, S.Y.;
ABSTRACT
Annual dose at the boundary of the interim storage facility at normal condition was calculated to estimate the site area of the facility of PWR spent nuclear fuel. In this work, source term was generated by ORIGEN-ARP for 4.5 wt% initial enrichment, 45,000 MWd/MTU burnup and 10 years cooling time. Modeling of the storage facilities and radiation shielding evaluations were conducted by MCNP code depending on the storage capacity. In the case of the centralized storage system, the required site area was found to have the radius of more than 700 m.
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