Measurement of radioactive gaseous effluents from voloxidation and dissolution of spent nuclear fuel [electronic resource]
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Online Access |
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Corporate Authors: | , |
Format: | Government Document Electronic eBook |
Language: | English |
Published: |
Aiken, S.C. : Oak Ridge, Tenn. :
United States. Dept. of Energy. Savannah River Site ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,
1978.
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Subjects: |
Abstract: | Laboratory-scale tests gave data on the release of tritium, ¹⁴C, ⁸⁵Kr, and ¹²⁹I as radioactive gases from spent nuclear fuels during voloxidation and dissolution. Voloxidation, a proposed reprocessing step, is intended to remove tritium from fuel by oxidation of UO₂ to U₃O₈ prior to dissolution of the fuel with nitric acid. ¹⁴C, ⁸⁵Kr, and ¹²⁹I may be evolved in both steps. Quantitative data from the tests may be used in designing off-gas treatment processes and equipment. The tests were performed in a shielded cell with a combination voloxidizer-dissolver. With a recirculating off-gas system, tritium and ¹⁴C were trapped on molecular sieves; ¹²⁹I was trapped on silver-exchanged zeolite. ⁸⁵Kr was measured by online gamma-ray counting. Zircaloy-clad UO₂ fuels from H. B. Robinson-2, Oconee-1, and Saxton reactors, with burnups from approximately 100 to approximately 28,000 MWD/MTHM, were tested. The results confirm that voloxidation released most of the tritium but only small fractions of the ¹⁴C, ⁸⁵Kr, and ¹²⁹I; the remainder of these radioactive gases evolved when the voloxidized fuels were dissolved. Voloxidation off-gases typically contained >99.8% of the tritium, 17 to 22% of the ¹⁴C, 7 to 17% of the ⁸⁵Kr, and <8% of the ¹²⁹I. Tritium evolved as HTO, with <0.1% as HT. |
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Item Description: | Published through SciTech Connect. 01/01/1978. "dp-ms-78-7" " conf-780819-21" 15. nuclear air cleaning conference, Boston, MA, USA, Aug 1978. Johnson, D.R.; Stone, J.A. |
Physical Description: | Pages: 15 : digital, PDF file. |