Environmentally acceptable nuclear fuel cycle development of a new reprocessing system
The aim of the present study is to establish a new reprocessing system for spent nuclear fuel, which would overcome the environmental problems in the nuclear fuel cycle. In order to achieve this, the following subjects have to be conquered: recoveries of high ratios of uranium and trans uranium elem...
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Veröffentlicht in: | Progress in nuclear energy (New series) 1998, Vol.32 (3), p.421-427 |
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Format: | Artikel |
Sprache: | eng |
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Zusammenfassung: | The aim of the present study is to establish a new reprocessing system for spent nuclear fuel, which would overcome the environmental problems in the nuclear fuel cycle. In order to achieve this, the following subjects have to be conquered: recoveries of high ratios of uranium and trans uranium elements from spent nuclear fuel, separations of strong radioactive elements, such as Sr and Cs, and assurance of the extreme safety during operation. The last subjects might be of particular importance in order to avoid any potential danger. Therefore, in the present system all processes were performed under mild aqueous conditions. Experiments were carried out for a simulated spent fuel solution, which was calculated from the ORIGEN CODE containing uranium and 17 major elements. The system consists of the following processes: 1. dissolution of spent UO
2 fuel involving off-gas treatment of I and Ru; 2. neutralization of the dissolved fuel solution with NaHCO
3Na
2CO
3 mixed solution to be slightly basic at pH about 9 followed by the separation of precipitated fission products by centrifugation; 3. separation of Cs by a precipitation method using tetraphenylborate ion; 4. recovery of U, Np and Pu as precipitates of hydrolyzed compounds from alkaline solution; 5. separation of Am and Cm from lanthanide elements. The concentration of residual uranium in the final solution was measured to be ppm order, indicating that the decontamination factor of U was as large as 10
4. Other hexa-valent actinide ions, NpO
2
2+ and PuO
2
2+, also have extremely large stability constants for the complex formation with carbonate ion, and are expected to behave similarly with UO
2
2+. In conclusion, the present reprocessing system enables us to recover U, Pu and Np from spent nuclear fuel by means of a simple precipitation method in much higher ratios compared with other reprocessing methods, to separate hazardous Cs and Sr from high-level waste, and to exclude any potential danger owing to chemical processes under mild aqueous conditions. |
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ISSN: | 0149-1970 |
DOI: | 10.1016/S0149-1970(97)00037-1 |