Study on Gaseous Effluent Treatment for Dissolution Step of Spent Nuclear Fuel Reprocessing

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Behavior of radioiodine and carbon-14 during spent fuel dissolution was studied in a bench-scale reprocessing test rig where 29 and 44 GWdt-1 spent fuels were respectively dissolved. Decontamination factor of AGS (silica-gel impregnated with silver nitrate) column for iodine-129 removal was measured to be more than 36,000. The measurement of iodine-129 profile in the adsorption column showed that the nuclide was effectively trapped by the adsorbent. Measurement of iodine-129 in the dissolver solution after the iodine-stripping operation using NO2 gas at 363 K, revealed that less than 0.57% of total iodine-129 generated, which was estimated by ORIGEN II calculation, was ... continued below

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9 pages

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Mineo, H.; Iizuka, M.; Fujisaki, S.; Hotoku, S.; Asakura, T. & Uchiyama, G. February 27, 2002.

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Behavior of radioiodine and carbon-14 during spent fuel dissolution was studied in a bench-scale reprocessing test rig where 29 and 44 GWdt-1 spent fuels were respectively dissolved. Decontamination factor of AGS (silica-gel impregnated with silver nitrate) column for iodine-129 removal was measured to be more than 36,000. The measurement of iodine-129 profile in the adsorption column showed that the nuclide was effectively trapped by the adsorbent. Measurement of iodine-129 in the dissolver solution after the iodine-stripping operation using NO2 gas at 363 K, revealed that less than 0.57% of total iodine-129 generated, which was estimated by ORIGEN II calculation, was remained in the dissolver solution. Also, measurement of iodine-129 by an iodine-stripping operation from the dissolver solution using potassium iodate showed that another 2.72% of total iodine-129 precipitated as iodide. In addition, about 70 % of total iodine generated was measured in the AGS columns. Rest of iodine-129 was supposed to adsorb to a HEPA filter and the inner surface of dissolver off-gas lines. Those results on iodine-129 distribution were found to be almost identical to the results obtained in the study using iodine-131 as tracer and the results reported by other works. It was demonstrated that the two-steps iodine-stripping method using potassium iodate could expel additional iodine from the solution, more effectively than iodine-stripping operation using NO2 gas. Iodine-131 was also detected on the AGS columns at the spent fuel dissolution. Increasing burnup showed larger amount of iodine-131 since amount of curium-244 contained in the spent fuel increased with the burnup. Release of carbon-14 as carbon dioxide during dissolution was found to occur when the release of krypton-85. From the 14CO2 measurement, initial nitrogen-14 concentration in the fuel was estimated to be about several ppm, which was within the range reported.

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9 pages

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  • Waste Management 2002 Symposium, Tucson, AZ (US), 02/24/2002--02/28/2002

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  • Report No.: none
  • Office of Scientific & Technical Information Report Number: 828968
  • Archival Resource Key: ark:/67531/metadc782627

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  • February 27, 2002

Added to The UNT Digital Library

  • Dec. 3, 2015, 9:30 a.m.

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  • April 27, 2016, 2:05 p.m.

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Mineo, H.; Iizuka, M.; Fujisaki, S.; Hotoku, S.; Asakura, T. & Uchiyama, G. Study on Gaseous Effluent Treatment for Dissolution Step of Spent Nuclear Fuel Reprocessing, article, February 27, 2002; Tucson, Arizona. (digital.library.unt.edu/ark:/67531/metadc782627/: accessed August 18, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.