earticle

영어

This study examines how much the radiation dose rate around it varies if a crack occurs on the spent nuclear fuel rod. Thespent nuclear fuel rod to be examined is that of Kori unit 3&4. The source terms are evaluated using the ORIGEN-ARPthat is part of the version 5.1 of the SCALE package. The radiation dose rate is assessed using the TORT. To check if thestructure of a fuel rod is appropriately modeled in the TORT calculation, the calculation results by the TORT arecompared with those by the ANISN for the same case. From the code simulation, it is known that if a crack occurs on thespent nuclear fuel rod, the neutron dose rate varies depending on what material is the crack filled with, but the gammadose rate varies irrespective of type of the material that the crack is filled with.