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机构地区:[1]中国科学院生态环境研究中心 [2]中国原子能科学研究院放射化学研究所
出 处:《核化学与放射化学》1997年第2期16-22,共7页Journal of Nuclear and Radiochemistry
摘 要:通过测定氚在30%TBP-煤油-HNO3间的分配比,探讨了氚在该体系中的萃取机理。实验发现,未经降解的溶剂中的氚易为水洗掉。其萃取机制为氚被两相中的HNO3和H2O中的H均匀稀释,而经辐照降解的溶剂(包括稀释剂及萃取剂和二者组成的溶液)其萃取的氚经洗涤后有明显的保留,在辐解的同时由于游离基反应而进入溶剂中的氚则更难洗下。为在动力堆乏燃料后处理中更好地控制氚的走向,建议采用高效、快速、分相完全的萃取装置。The extraction mechanism of tritium has been studied by determining the distribution coefficient of tritium in 30%TBP kerosene HNO 3 H 2O system.It has been found that tritium in unirradiated solvent is easy to be washed out with water.The mechanism of tritium extraction is based on the well distributed dilution of tritium between two phases.There is an obvious retention of tritium in the solvent after washing of irradiated solvent by water.Some of tritium enter the structure of solvents during the irradiation period by free radical polymerization reaction.So we propose to use the highly efficient equipments which can isolate the organic phase and aqueous phase rapidly and completely in order to control the trend of tritium in reprocessing process of spent fuel from power reactous.
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