The Variation of CANDU Spent Fuel Characteristics During Surface Storage

The aim of this work is to present the results obtained from the irradiation of a CANDU 6 fuel assembly within a time of 327 days with a 23,853 MW/t
U
cycle specific power followed by a 50-year decay, using the ORIGEN and ARP calculation codes which are included in the SCALE 6.2.2. code system. The ORIGEN library was prepared by ARP to have three sets of burnup-dependent transition cross-sections, resulting in three cases, one for each of the irradiation intervals proposed by the study: 100, 100, 127 days at a maximum fuel burnup of 7800 MW.day/tU. The input material has been specified to have 1 ton of metallic uranium with an enrichment of 0.7145% in U
²³⁵
. Simulating the irradiation of nuclear fuel within the reactor leads to the follow up of its radiological characteristics, required in the stages of surface storage as radioactive waste.