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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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| Published in: | Nuclear engineering and design 2014-10, Vol.277 (C), p.163-165 |
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| Main Authors: | , , , , , , , |
| Format: | Article |
| Language: | English |
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| Online Access: | Get full text |
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| cites | cdi_FETCH-LOGICAL-c337t-d5cb7b564c1015e5cbe8575efd93c2232f02e22df9dfbb889a0df4e60af191f63 |
| container_end_page | 165 |
| container_issue | C |
| container_start_page | 163 |
| container_title | Nuclear engineering and design |
| container_volume | 277 |
| creator | Alikulov, Sh. A. Baytelesov, S.A. Boltaboev, A.F. Kungurov, F.R. Menlove, H.O. O’Connor, W. Osmanov, B.S. Salikhbaev, U.S. |
| description | •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%. |
| doi_str_mv | 10.1016/j.nucengdes.2014.06.020 |
| format | article |
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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%.</abstract><cop>Netherlands</cop><pub>Elsevier B.V</pub><doi>10.1016/j.nucengdes.2014.06.020</doi><tpages>3</tpages><oa>free_for_read</oa></addata></record> |
| fulltext | fulltext |
| identifier | ISSN: 0029-5493 |
| ispartof | Nuclear engineering and design, 2014-10, Vol.277 (C), p.163-165 |
| issn | 0029-5493 1872-759X |
| language | eng |
| recordid | cdi_osti_scitechconnect_1575813 |
| source | Elsevier:Jisc Collections:Elsevier Read and Publish Agreement 2022-2024:Freedom Collection (Reading list) |
| title | Experimental studies of spent fuel burn-up in WWR-SM reactor |
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