Effect of burn-up on the radioactivation behavior of cladding hull materials studied using the ORIGEN-S code

The effect of fuel burn-up on the radioactivation behavior of cladding hull materials was investigated using the ORIGEN-S code for various materials of Zircaloy-4, Zirlo, HANA-4, and HANA-6 and for various fuel burn-ups of 30, 45, 60, and 75 GWD/MTU. The Zircaloy-4 material is the only one that does...

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Bibliographic Details
Published in:Journal of radioanalytical and nuclear chemistry 2013-12, Vol.298 (3), p.1629-1633
Main Authors: Jeon, Min Ku, Lee, Chang Hwa, Park, Chang Je, Choi, Jung Hoon, Cho, In Hak, Kang, Kweon Ho, Park, Hwan-Seo, Park, Geun Il
Format: Article
Language:English
Subjects:
Alloys
Building materials
Chemistry
Chemistry and Materials Science
Cladding
Constituents
Diagnostic Radiology
Fuel consumption
Fuels
Hadrons
Heavy Ions
Inorganic Chemistry
Nuclear Chemistry
Nuclear Physics
Physical Chemistry
Radioactivation
Radioactivity
Recovery
Repositories
Zirconium base alloys
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Summary:The effect of fuel burn-up on the radioactivation behavior of cladding hull materials was investigated using the ORIGEN-S code for various materials of Zircaloy-4, Zirlo, HANA-4, and HANA-6 and for various fuel burn-ups of 30, 45, 60, and 75 GWD/MTU. The Zircaloy-4 material is the only one that does not contain Nb as an alloy constituent, and it was revealed that 125 Sb, 125m Te, and 55 Fe are the major sources of radioactivity. On the other hand, 93m Nb was identified as the most radioactive nuclide for the other materials although minor radioactive nuclides varied owing to their different initial constituents. The radioactivity of 94 Nb was of particular focus owing to its acceptance limit against a Korean intermediate-/low-level waste repository. The radioactivation calculation results revealed that only Zircaloy-4 is acceptable for the Korean repository, while the other materials required at least 4,900 of Nb decontamination factor owing to the high radioactivity of 94 Nb regardless of the fuel burn-up. A discussion was also made on the feasibility of Zr recovery methods (chlorination and electrorefining) for selective recovery of Zr so that it can be disposed of in the Korean repository.
ISSN:0236-5731
1588-2780
DOI:10.1007/s10967-013-2543-6