Experimental studies of spent fuel burn-up in WWR-SM reactor

•Uranium burn-up measurement from 137Cs activity in spent reactor fuel.•Comparison to reference sample with known burn-up value (ratio method).•Cross-check of the approach with neutron-based measurement technique. The article reports the results of 235U burn-up measurements using 137Cs activity tech...

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Bibliographic Details
Published in:Nuclear engineering and design 2014-10, Vol.277 (C), p.163-165
Main Authors: Alikulov, Sh. A., Baytelesov, S.A., Boltaboev, A.F., Kungurov, F.R., Menlove, H.O., O’Connor, W., Osmanov, B.S., Salikhbaev, U.S.
Format: Article
Language:English
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Summary:•Uranium burn-up measurement from 137Cs activity in spent reactor fuel.•Comparison to reference sample with known burn-up value (ratio method).•Cross-check of the approach with neutron-based measurement technique. The article reports the results of 235U burn-up measurements using 137Cs activity technique for 12 nuclear fuel assemblies of WWR-SM research reactor after 3-year cooling time. The discrepancy between the measured and the calculated burn-up values was about 3%. To increase the reliability of the data and for cross-check purposes, neutron measurement approach was also used. Average discrepancy between two methods was around 12%.
ISSN:0029-5493
1872-759X
DOI:10.1016/j.nucengdes.2014.06.020