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AN ASSESSMENT OF THE RADIATION DOSE RATE DUE TO AN OCCURRENCE OF THE DEFECT ON THE SPENT NUCLEAR FUEL ROD  

Lee, Sang-Hun (Department of Energy & Environment System Engineering, Dongguk University)
Moon, Joo-Hyun (Department of Energy & Environment System Engineering, Dongguk University)
Publication Information
Journal of Radiation Protection and Research / v.34, no.3, 2009 , pp. 144-150 More about this Journal
Abstract
This study examines how much the radiation dose rate around it varies if a crack occurs on the spent nuclear fuel rod. The spent nuclear fuel rod to be examined is that of Kori unit 3&4. The source terms are evaluated using the ORIGEN-ARP that is part of the version 5.1 of the SCALE package. The radiation dose rate is assessed using the TORT. To check if the structure of a fuel rod is appropriately modeled in the TORT calculation, the calculation results by the TORT are compared with those by the ANISN for the same case. From the code simulation, it is known that if a crack occurs on the spent nuclear fuel rod, the neutron dose rate varies depending on what material is the crack filled with, but the gamma dose rate varies irrespective of type of the material that the crack is filled with.
Keywords
Spent Nuclear Fuel Rod; Crack; Source Term; Radiation Dose; Neutron Dose; Gamma Dose;
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