LABORATORY STUDY ON THE CHLORINATION REPROCESSING OF NEUTRON-IRRADIATED URANIUM FUELS. 4. PRODUCTION AND PROPERTIES OF ZIRCONIUM-PHOSPHATE-SILICATE EXCHANGE MATERIAL AND ITS APPLICATION FOR PLUTONIUM ISOLATION (in German)
For the separation of plutonium from fission products, large amounts of radiation-resistant exchangers are necessary. Synthetic inorganic exchangers were prepared with zirconium phosphate silicate (ZPS) as the base. The characterization of their exchange properties yielded capacity values of 2.5 milliequivalents per gram at pH 7. They possess especially favorable separation properties for plutonium. Therefore, the ZPS was inserted for plutonium isolation after the chlorination of irradiated UO/sub 2/ and the gas- chromatographic separation of chloride vapors (700 deg C) on charcoal. For plutonium in a single passage on ZPS a total separation factor of 0.6 x 10/sup 3/ was obtained, which can be improved by further operations. (tr-auth)
- Research Organization:
- Zentralinstitut fur Kernphysik, Rossendorf, Ger.
- NSA Number:
- NSA-17-027499
- OSTI ID:
- 4714723
- Journal Information:
- Kernenergie (East Germany), Journal Name: Kernenergie (East Germany) Vol. Vol: 6; ISSN KERNA
- Country of Publication:
- Country unknown/Code not available
- Language:
- German
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