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Radioactivity Analysis of DUPIC Fuel Fabrication Process According to Burn-Up and Cooling Time

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Abstract:

A radioactivity analysis of OREOX and the sintering steps for the DUPIC fuel fabrication process has been conducted. This study utilized ORIGEN2 code to calculate and analyze the radioactivity of spent fuels for various burn-up and cooling times. The analysis results have shown that the activity reduction of spent fuels after DUPIC fuel fabrication process was 40∼51 % and higher with longer burn-up and cooling times. This study also shows that the distribution of gaseous waste generated from OREOX process is mainly attributed to Kr, Ru and H-3, regardless of burn-up and cooling times. On the other hand, in the off-gas of the sintering process, the radioactivity distribution of Cs is more than 98 %, regardless of burn-up and cooling times.

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Periodical:

Key Engineering Materials (Volumes 277-279)

Pages:

475-480

DOI:

https://doi.org/10.4028/www.scientific.net/KEM.277-279.475

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Online since:

January 2005

Authors:

Jin Myeong Shin, Jang Jin Park, Seol Woo Shin, Myung Seung Yang, Ho Hee Lee

Keywords:

DUPIC Fuel, Off-Gas Treatment, Radioactivity Analysis, Radioactivity Reduction

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© 2005 Trans Tech Publications Ltd. All Rights Reserved

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References

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