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Burnup Measurement of Spent Fuel Assembly by CZT-based Gamma-Ray Spectroscopy for Input Nuclear Material Accountability of Pyroprocessing

Input nuclear material accountability is crucial for a pyroprocessing facility safeguards. Until a direct Pu measurement technique is established, an indirect method based on code calculations with burnup measurement and neutron counting for 244 Cm could be a practical option. Burnup can be determin...

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Bibliographic Details
Published in:IEEE transactions on nuclear science 2014-08, Vol.61 (4), p.2169-2174
Main Authors: Seo, Hee, Oh, Jong-Myeong, Shin, Hee-Sung, Kim, Ho-Dong, Lee, Seung Kyu, Lee, Hyun Su, Park, Se-Hwan
Format: Article
Language:English
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Summary:Input nuclear material accountability is crucial for a pyroprocessing facility safeguards. Until a direct Pu measurement technique is established, an indirect method based on code calculations with burnup measurement and neutron counting for 244 Cm could be a practical option. Burnup can be determined by destructive analysis (DA) for final dispositive accuracy or by nondestructive assay (NDA) for near-real time accountancy. In the present study, an underwater burnup measurement system based on gamma-ray spectroscopy with the CZT detector was developed and tested on a spent fuel assembly. Burnup was determined according to the 134 Cs/ 137 Cs activity ratio with efficiency correction by Geant4 Monte Carlo simulations. The activity ratio as a function of burnup was obtained by ORIGEN calculations. The measured burnup error was 8.6%, which was within the measurement uncertainty. It is expected that the underwater burnup measurement system could fulfill an important role as a means of near-real time accountancy at a future pyroprocessing facility.
ISSN:0018-9499
1558-1578
DOI:10.1109/TNS.2014.2319331