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Giuseppe Modolo, Reinhard Odoj
Nuclear Technology | Volume 117 | Number 1 | January 1997 | Pages 80-86
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT97-A35337
Articles are hosted by Taylor and Francis Online.
According to the current state of the art in reprocessing technology, the 129I contained in spent fuel elements can be completely transferred to the dissolver off-gas and efficiently adsorbed on AgNO3-impregnated silica (AC 6120). For future transmutation, the 129I should again be separated selectively and as completely as possible (>99%) from the AC 6120 adsorption matrix. Experimental studies show that a quantitative recovery of the iodine is possible by wet chemical and thermal processes. Extraction experiments using iodine-loaded AC 6120 with sodium sulfide solution provide recovery rates of 99 ± 1%. Reduction with hydrogen at 500°C, in which gaseous HI was liberated, provided recovery rates of >99%. After the separation of iodine, the reduced AC 6120 can be used again as an adsorbent for molecular iodine.