I-129 targets for studies of nuclear waste transmutation

摘要

Nuclear incineration of long-lived fission products and minor actinides is being investigated as an alternative means of reactor waste disposal. I-129 is of particular interest because of its long half-life and high mobility in the environment. Lead iodide targets of I-129 for neutron capture cross-section measurements were prepared from 2 10 1 fuel reprocessing waste solution containing 1.3 g l(-1) iodine and other fission products, The iodine was separated by oxidation to I-2 and extraction into chloroform, reduction to iodide by sodium sulphite and re-extraction into an aqueous phase. Iodide was precipitated using lead nitrate and dried. The chemistry was carried out batch-wise using 400 ml starting solution each time and recycling the chloroform. An extraction efficiency of about 90, determined by gamma-ray spectrometry, was achieved. (C) 2001 Elsevier Science B.V. All rights reserved. References: 15