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Preliminary Analysis of Dose Rate Variation on the Containment Building Wall of Dry Interim Storage Facilities for PWR Spent Nuclear Fuel
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 Title & Authors
Preliminary Analysis of Dose Rate Variation on the Containment Building Wall of Dry Interim Storage Facilities for PWR Spent Nuclear Fuel
Seo, M.H.; Yoon, J.H.; Cha, G.Y.;
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 Abstract
Annual dose on the containment building wall of the interim storage facility at normal condition was calculated to estimate the dose rate transition of the facility of PWR spent nuclear fuel. In this study, source term was generated by ORIGEN-ARP with 4.5 wt% initial enrichment, 45,000 MWd/MTU burnup and 10 years cooling time. Modeling of the storage facility and the containment building and radiation shielding evaluations were conducted by MCNP code depending on the distance between the wall and the facility in the building. In the case of the centralized storage system, the distance required for the annual dose rate limit from 10CFR72 was estimated to be 50 m.
 Keywords
Annual dose rate;10CFR72;MCNP;PWR spent nuclear fuel;Interim storage facility;Containment building;
 Language
Korean
 Cited by
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